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nuclear fuel</title> <meta name="description" content="Search results for: spent nuclear fuel"> <meta name="keywords" content="spent nuclear fuel"> <meta name="viewport" content="width=device-width, initial-scale=1, minimum-scale=1, maximum-scale=1, user-scalable=no"> <meta charset="utf-8"> <link href="https://cdn.waset.org/favicon.ico" type="image/x-icon" rel="shortcut icon"> <link href="https://cdn.waset.org/static/plugins/bootstrap-4.2.1/css/bootstrap.min.css" rel="stylesheet"> <link href="https://cdn.waset.org/static/plugins/fontawesome/css/all.min.css" rel="stylesheet"> <link href="https://cdn.waset.org/static/css/site.css?v=150220211555" rel="stylesheet"> </head> <body> <header> <div class="container"> <nav class="navbar navbar-expand-lg navbar-light"> <a class="navbar-brand" href="https://waset.org"> <img src="https://cdn.waset.org/static/images/wasetc.png" alt="Open Science Research Excellence" title="Open Science Research Excellence" /> </a> <button class="d-block d-lg-none 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action="https://publications.waset.org/abstracts/search"> <div id="custom-search-input"> <div class="input-group"> <i class="fas fa-search"></i> <input type="text" class="search-query" name="q" placeholder="Author, Title, Abstract, Keywords" value="spent nuclear fuel"> <input type="submit" class="btn_search" value="Search"> </div> </div> </form> </div> </div> <div class="row mt-3"> <div class="col-sm-3"> <div class="card"> <div class="card-body"><strong>Commenced</strong> in January 2007</div> </div> </div> <div class="col-sm-3"> <div class="card"> <div class="card-body"><strong>Frequency:</strong> Monthly</div> </div> </div> <div class="col-sm-3"> <div class="card"> <div class="card-body"><strong>Edition:</strong> International</div> </div> </div> <div class="col-sm-3"> <div class="card"> <div class="card-body"><strong>Paper Count:</strong> 2846</div> </div> </div> </div> <h1 class="mt-3 mb-3 text-center" style="font-size:1.6rem;">Search results for: spent nuclear fuel</h1> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2846</span> Two-Dimensional Modeling of Spent Nuclear Fuel Using FLUENT</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Imane%20Khalil">Imane Khalil</a>, <a href="https://publications.waset.org/abstracts/search?q=Quinn%20Pratt"> Quinn Pratt</a> </p> <p class="card-text"><strong>Abstract:</strong></p> In a nuclear reactor, an array of fuel rods containing stacked uranium dioxide pellets clad with zircalloy is the heat source for a thermodynamic cycle of energy conversion from heat to electricity. After fuel is used in a nuclear reactor, the assemblies are stored underwater in a spent nuclear fuel pool at the nuclear power plant while heat generation and radioactive decay rates decrease before it is placed in packages for dry storage or transportation. A computational model of a Boiling Water Reactor spent fuel assembly is modeled using FLUENT, the computational fluid dynamics package. Heat transfer simulations were performed on the two-dimensional 9x9 spent fuel assembly to predict the maximum cladding temperature for different input to the FLUENT model. Uncertainty quantification is used to predict the heat transfer and the maximum temperature profile inside the assembly. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=spent%20nuclear%20fuel" title="spent nuclear fuel">spent nuclear fuel</a>, <a href="https://publications.waset.org/abstracts/search?q=conduction" title=" conduction"> conduction</a>, <a href="https://publications.waset.org/abstracts/search?q=heat%20transfer" title=" heat transfer"> heat transfer</a>, <a href="https://publications.waset.org/abstracts/search?q=uncertainty%20quantification" title=" uncertainty quantification"> uncertainty quantification</a> </p> <a href="https://publications.waset.org/abstracts/86958/two-dimensional-modeling-of-spent-nuclear-fuel-using-fluent" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/86958.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">220</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2845</span> Comparative Analysis of Local Acceptance of Renewable Energy Facilities and Spent Nuclear Fuel Repositories</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Taehyun%20Kim">Taehyun Kim</a>, <a href="https://publications.waset.org/abstracts/search?q=Hyunjoo%20Park"> Hyunjoo Park</a>, <a href="https://publications.waset.org/abstracts/search?q=Taehyun%20Kim"> Taehyun Kim</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Public deliberation committee on Shin-Gori Nuclear Reactors No. 5 & 6 in South Korea recently suggested policy recommendation in July 2017 including complementary measures for resumption of construction: 1) nuclear power generation reduction, 2) expansion of investment to increase proportion of renewable energy, 3) repositories of spent nuclear fuel. Even when constructing eco-friendly renewable energy facilities such as solar and wind power plants, local residents are opposed to construction of these facilities due to environmental pollution and health impacts. In order to transform eco-friendly energy, it is necessary to convert nuclear energy into renewable energy and to take measures to increase the acceptance of residents through the participation of citizens. Therefore, this study aims to compare the factors of local acceptance of renewable energy facilities and spent nuclear fuel repositories through literature review and in-depth interview. The results show that environmental and economic concerns, risk perceptions, sociality, demographic characteristics and subjective recognition types affect the local acceptance for spent nuclear fuel repository. The factors of local acceptance for renewable energy facilities are partially coincide with those for spent nuclear fuel repository. The results of this study will contribute to improving residents' acceptance and reducing conflicts when determining the location of facilities in the future. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=local%20acceptance" title="local acceptance">local acceptance</a>, <a href="https://publications.waset.org/abstracts/search?q=renewable%20energy%20facility" title=" renewable energy facility"> renewable energy facility</a>, <a href="https://publications.waset.org/abstracts/search?q=spent%20nuclear%20fuel%20repository" title=" spent nuclear fuel repository"> spent nuclear fuel repository</a>, <a href="https://publications.waset.org/abstracts/search?q=interview" title=" interview"> interview</a> </p> <a href="https://publications.waset.org/abstracts/96119/comparative-analysis-of-local-acceptance-of-renewable-energy-facilities-and-spent-nuclear-fuel-repositories" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/96119.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">301</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2844</span> Pool Fire Tests of Dual Purpose Casks for Spent Nuclear Fuel</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=K.%20S.%20Bang">K. S. Bang</a>, <a href="https://publications.waset.org/abstracts/search?q=S.%20H.%20Yu"> S. H. Yu</a>, <a href="https://publications.waset.org/abstracts/search?q=J.%20C.%20Lee"> J. C. Lee</a>, <a href="https://publications.waset.org/abstracts/search?q=K.%20S.%20Seo"> K. S. Seo</a>, <a href="https://publications.waset.org/abstracts/search?q=S.%20H.%20Lee"> S. H. Lee</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Dual purpose casks are used for storage and transport of spent nuclear fuel assemblies. Therefore, they satisfy the requirements prescribed in the Korea NSSC Act 2013-27, the IAEA Safety Standard Series No. SSR-6, and US 10 CFR Part 71. These regulatory guidelines classify the dual purpose cask as a Type B package, and state that a Type B package must be able to withstand a temperature of 800°C for a period of 30 min. Therefore, a fire test was conducted using a one-sixth slice of a real cask to estimate the thermal integrity of the dual purpose cask at a temperature of 800°C. The neutron shield reached a maximum temperature of 183°C, which indicates that dual purpose cask was properly insulated from the heat of the flames. The temperature rise of the basket during the fire test was 29°C. Therefore, the integrity of a spent nuclear fuel is estimated to be maintained. The temperature was lower when a cooling pin was installed. The neutron shielding was therefore protected adequately by cooling pin. As a result, the thermal integrity of the dual purpose cask was maintained and the cask is judged to be sufficiently safe for temperatures under 800°C. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=dual%20purpose%20cask" title="dual purpose cask">dual purpose cask</a>, <a href="https://publications.waset.org/abstracts/search?q=spent%20nuclear%20fuel" title=" spent nuclear fuel"> spent nuclear fuel</a>, <a href="https://publications.waset.org/abstracts/search?q=pool%20fire%20test" title=" pool fire test"> pool fire test</a>, <a href="https://publications.waset.org/abstracts/search?q=integrity" title=" integrity"> integrity</a> </p> <a href="https://publications.waset.org/abstracts/28403/pool-fire-tests-of-dual-purpose-casks-for-spent-nuclear-fuel" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/28403.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">461</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2843</span> The Model Establishment and Analysis of TRACE/FRAPTRAN for Chinshan Nuclear Power Plant Spent Fuel Pool</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=J.%20R.%20Wang">J. R. Wang</a>, <a href="https://publications.waset.org/abstracts/search?q=H.%20T.%20Lin"> H. T. Lin</a>, <a href="https://publications.waset.org/abstracts/search?q=Y.%20S.%20Tseng"> Y. S. Tseng</a>, <a href="https://publications.waset.org/abstracts/search?q=W.%20Y.%20Li"> W. Y. Li</a>, <a href="https://publications.waset.org/abstracts/search?q=H.%20C.%20Chen"> H. C. Chen</a>, <a href="https://publications.waset.org/abstracts/search?q=S.%20W.%20Chen"> S. W. Chen</a>, <a href="https://publications.waset.org/abstracts/search?q=C.%20Shih"> C. Shih</a> </p> <p class="card-text"><strong>Abstract:</strong></p> TRACE is developed by U.S. NRC for the nuclear power plants (NPPs) safety analysis. We focus on the establishment and application of TRACE/FRAPTRAN/SNAP models for Chinshan NPP (BWR/4) spent fuel pool in this research. The geometry is 12.17 m × 7.87 m × 11.61 m for the spent fuel pool. In this study, there are three TRACE/SNAP models: one-channel, two-channel, and multi-channel TRACE/SNAP model. Additionally, the cooling system failure of the spent fuel pool was simulated and analyzed by using the above models. According to the analysis results, the peak cladding temperature response was more accurate in the multi-channel TRACE/SNAP model. The results depicted that the uncovered of the fuels occurred at 2.7 day after the cooling system failed. In order to estimate the detailed fuel rods performance, FRAPTRAN code was used in this research. According to the results of FRAPTRAN, the highest cladding temperature located on the node 21 of the fuel rod (the highest node at node 23) and the cladding burst roughly after 3.7 day. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=TRACE" title="TRACE">TRACE</a>, <a href="https://publications.waset.org/abstracts/search?q=FRAPTRAN" title=" FRAPTRAN"> FRAPTRAN</a>, <a href="https://publications.waset.org/abstracts/search?q=BWR" title=" BWR"> BWR</a>, <a href="https://publications.waset.org/abstracts/search?q=spent%20fuel%20pool" title=" spent fuel pool"> spent fuel pool</a> </p> <a href="https://publications.waset.org/abstracts/49105/the-model-establishment-and-analysis-of-tracefraptran-for-chinshan-nuclear-power-plant-spent-fuel-pool" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/49105.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">357</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2842</span> Probabilistic Safety Assessment of Koeberg Spent Fuel Pool</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Sibongiseni%20Thabethe">Sibongiseni Thabethe</a>, <a href="https://publications.waset.org/abstracts/search?q=Ian%20Korir"> Ian Korir</a> </p> <p class="card-text"><strong>Abstract:</strong></p> The effective management of spent fuel pool (SFP) safety has been raised as one of the emerging issues to further enhance nuclear installation safety after the Fukushima accident on March 11, 2011. Before then, SFP safety-related issues have been mainly focused on (a) controlling the configuration of the fuel assemblies in the pool with no loss of pool coolants and (b) ensuring adequate pool storage space to prevent fuel criticality owing to chain reactions of the fission products and the ability for neutron absorption to keep the fuel cool. A probabilistic safety (PSA) assessment was performed using the systems analysis program for hands-on integrated reliability evaluations (SAPHIRE) computer code. Event and fault tree analysis was done to develop a PSA model for the Koeberg SFP. We present preliminary PSA results of events that lead to boiling and cause fuel uncovering, resulting in possible fuel damage in the Koeberg SFP. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=computer%20code" title="computer code">computer code</a>, <a href="https://publications.waset.org/abstracts/search?q=fuel%20assemblies" title=" fuel assemblies"> fuel assemblies</a>, <a href="https://publications.waset.org/abstracts/search?q=probabilistic%20risk%20assessment" title=" probabilistic risk assessment"> probabilistic risk assessment</a>, <a href="https://publications.waset.org/abstracts/search?q=spent%20fuel%20pool" title=" spent fuel pool"> spent fuel pool</a> </p> <a href="https://publications.waset.org/abstracts/131191/probabilistic-safety-assessment-of-koeberg-spent-fuel-pool" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/131191.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">169</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2841</span> The Model Establishment and Analysis of TRACE/MELCOR for Kuosheng Nuclear Power Plant Spent Fuel Pool</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=W.%20S.%20Hsu">W. S. Hsu</a>, <a href="https://publications.waset.org/abstracts/search?q=Y.%20Chiang"> Y. Chiang</a>, <a href="https://publications.waset.org/abstracts/search?q=Y.%20S.%20Tseng"> Y. S. Tseng</a>, <a href="https://publications.waset.org/abstracts/search?q=J.%20R.%20Wang"> J. R. Wang</a>, <a href="https://publications.waset.org/abstracts/search?q=C.%20Shih"> C. Shih</a>, <a href="https://publications.waset.org/abstracts/search?q=S.%20W.%20Chen"> S. W. Chen</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Kuosheng nuclear power plant (NPP) is a BWR/6 plant in Taiwan. There is more concern for the safety of NPPs in Taiwan after Japan Fukushima NPP disaster occurred. Hence, in order to estimate the safety of Kuosheng NPP spent fuel pool (SFP), by using TRACE, MELCOR, and SNAP codes, the safety analysis of Kuosheng NPP SFP was performed. There were two main steps in this research. First, the Kuosheng NPP SFP models were established. Second, the transient analysis of Kuosheng SFP was done by TRACE and MELCOR under the cooling system failure condition (Fukushima-like condition). The results showed that the calculations of MELCOR and TRACE were very similar in this case, and the fuel uncover happened roughly at 4<sup>th</sup> day after the failure of cooling system. The above results indicated that Kuosheng NPP SFP may be unsafe in the case of long-term SBO situation. In addition, future calculations were needed to be done by the other codes like FRAPTRAN for the cladding calculations. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=TRACE" title="TRACE">TRACE</a>, <a href="https://publications.waset.org/abstracts/search?q=MELCOR" title=" MELCOR"> MELCOR</a>, <a href="https://publications.waset.org/abstracts/search?q=SNAP" title=" SNAP"> SNAP</a>, <a href="https://publications.waset.org/abstracts/search?q=spent%20fuel%20pool" title=" spent fuel pool"> spent fuel pool</a> </p> <a href="https://publications.waset.org/abstracts/57025/the-model-establishment-and-analysis-of-tracemelcor-for-kuosheng-nuclear-power-plant-spent-fuel-pool" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/57025.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">331</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2840</span> Online Measurement of Fuel Stack Elongation</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Sung%20Ho%20Ahn">Sung Ho Ahn</a>, <a href="https://publications.waset.org/abstracts/search?q=Jintae%20Hong"> Jintae Hong</a>, <a href="https://publications.waset.org/abstracts/search?q=Chang%20Young%20Joung"> Chang Young Joung</a>, <a href="https://publications.waset.org/abstracts/search?q=Tae%20Ho%20Yang"> Tae Ho Yang</a>, <a href="https://publications.waset.org/abstracts/search?q=Sung%20Ho%20Heo"> Sung Ho Heo</a>, <a href="https://publications.waset.org/abstracts/search?q=Seo%20Yun%20Jang"> Seo Yun Jang</a> </p> <p class="card-text"><strong>Abstract:</strong></p> The performances of nuclear fuels and materials are qualified at an irradiation system in research reactors operating under the commercial nuclear power plant conditions. Fuel centerline temperature, coolant temperature, neutron flux, deformations of fuel stack and swelling are important parameters needed to analyze the nuclear fuel performances. The dimensional stability of nuclear fuels is a key parameter measuring the fuel densification and swelling. In this study, the fuel stack elongation is measured using a LVDT. A mockup LVDT instrumented fuel rod is developed. The performances of mockup LVDT instrumented fuel rod is evaluated by experiments. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=axial%20deformation" title="axial deformation">axial deformation</a>, <a href="https://publications.waset.org/abstracts/search?q=elongation%20measurement" title=" elongation measurement"> elongation measurement</a>, <a href="https://publications.waset.org/abstracts/search?q=in-pile%20instrumentation" title=" in-pile instrumentation"> in-pile instrumentation</a>, <a href="https://publications.waset.org/abstracts/search?q=LVDT" title=" LVDT"> LVDT</a> </p> <a href="https://publications.waset.org/abstracts/46795/online-measurement-of-fuel-stack-elongation" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/46795.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">534</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2839</span> Estimation of Hydrogen Production from PWR Spent Fuel Due to Alpha Radiolysis</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Sivakumar%20Kottapalli">Sivakumar Kottapalli</a>, <a href="https://publications.waset.org/abstracts/search?q=Abdesselam%20Abdelouas"> Abdesselam Abdelouas</a>, <a href="https://publications.waset.org/abstracts/search?q=Christoph%20Hartnack"> Christoph Hartnack</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Spent nuclear fuel generates a mixed field of ionizing radiation to the water. This radiation field is generally dominated by gamma rays and a limited flux of fast neutrons. The fuel cladding effectively attenuates beta and alpha particle radiation. Small fraction of the spent nuclear fuel exhibits some degree of fuel cladding penetration due to pitting corrosion and mechanical failure. Breaches in the fuel cladding allow the exposure of small volumes of water in the cask to alpha and beta ionizing radiation. The safety of the transport of radioactive material is assured by the package complying with the IAEA Requirements for the Safe Transport of Radioactive Material SSR-6. It is of high interest to avoid generation of hydrogen inside the cavity which may to an explosive mixture. The risk of hydrogen production along with other radiation gases should be analyzed for a typical spent fuel for safety issues. This work aims to perform a realistic study of the production of hydrogen by radiolysis assuming most penalizing initial conditions. It consists in the calculation of the radionuclide inventory of a pellet taking into account the burn up and decays. Westinghouse 17X17 PWR fuel has been chosen and data has been analyzed for different sets of enrichment, burnup, cycles of irradiation and storage conditions. The inventory is calculated as the entry point for the simulation studies of hydrogen production by radiolysis kinetic models by MAKSIMA-CHEMIST. Dose rates decrease strongly within ~45 μm from the fuel surface towards the solution(water) in case of alpha radiation, while the dose rate decrease is lower in case of beta and even slower in case of gamma radiation. Calculations are carried out to obtain spectra as a function of time. Radiation dose rate profiles are taken as the input data for the iterative calculations. Hydrogen yield has been found to be around 0.02 mol/L. Calculations have been performed for a realistic scenario considering a capsule containing the spent fuel rod. Thus, hydrogen yield has been debated. Experiments are under progress to validate the hydrogen production rate using cyclotron at > 5MeV (at ARRONAX, Nantes). <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=radiolysis" title="radiolysis">radiolysis</a>, <a href="https://publications.waset.org/abstracts/search?q=spent%20fuel" title=" spent fuel"> spent fuel</a>, <a href="https://publications.waset.org/abstracts/search?q=hydrogen" title=" hydrogen"> hydrogen</a>, <a href="https://publications.waset.org/abstracts/search?q=cyclotron" title=" cyclotron"> cyclotron</a> </p> <a href="https://publications.waset.org/abstracts/34769/estimation-of-hydrogen-production-from-pwr-spent-fuel-due-to-alpha-radiolysis" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/34769.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">521</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2838</span> The Mitigation Strategy Analysis of Kuosheng Nuclear Power Plant Spent Fuel Pool Using MELCOR2.1/SNAP</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Y.%20Chiang">Y. Chiang</a>, <a href="https://publications.waset.org/abstracts/search?q=J.%20R.%20Wang"> J. R. Wang</a>, <a href="https://publications.waset.org/abstracts/search?q=J.%20H.%20Yang"> J. H. Yang</a>, <a href="https://publications.waset.org/abstracts/search?q=Y.%20S.%20Tseng"> Y. S. Tseng</a>, <a href="https://publications.waset.org/abstracts/search?q=C.%20Shih"> C. Shih</a>, <a href="https://publications.waset.org/abstracts/search?q=S.%20W.%20Chen"> S. W. Chen</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Kuosheng nuclear power plant (NPP) is a BWR/6 plant in Taiwan. There is more concern for the safety of Spent Fuel Pools (SFPs) in Taiwan after Fukushima event. In order to estimate the safety of Kuosheng NPP SFP, by using MELCOR2.1 and SNAP, the safety analysis of Kuosheng NPP SFP was performed combined with the mitigation strategy of NEI 06-12 report. There were several steps in this research. First, the Kuosheng NPP SFP models were established by MELCOR2.1/SNAP. Second, the Station Blackout (SBO) analysis of Kuosheng SFP was done by TRACE and MELCOR under the cooling system failure condition. The results showed that the calculations of MELCOR and TRACE were very similar in this case. Second, the mitigation strategy analysis was done with the MELCOR model by following the NEI 06-12 report. The results showed the effectiveness of NEI 06-12 strategy in Kuosheng NPP SFP. Finally, a sensitivity study of SFP quenching was done to check the differences of different water injection time and the phenomena during the quenching. The results showed that if the cladding temperature was over 1600 K, the water injection may have chance to cause the accident more severe with more hydrogen generation. It was because of the oxidation heat and the “Breakaway” effect of the zirconium-water reaction. An animation model built by SNAP was also shown in this study. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=MELCOR" title="MELCOR">MELCOR</a>, <a href="https://publications.waset.org/abstracts/search?q=SNAP" title=" SNAP"> SNAP</a>, <a href="https://publications.waset.org/abstracts/search?q=spent%20fuel%20pool" title=" spent fuel pool"> spent fuel pool</a>, <a href="https://publications.waset.org/abstracts/search?q=quenching" title=" quenching"> quenching</a> </p> <a href="https://publications.waset.org/abstracts/67490/the-mitigation-strategy-analysis-of-kuosheng-nuclear-power-plant-spent-fuel-pool-using-melcor21snap" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/67490.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">359</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2837</span> Development of Scenarios for Sustainable Next Generation Nuclear System </h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Muhammad%20Minhaj%20Khan">Muhammad Minhaj Khan</a>, <a href="https://publications.waset.org/abstracts/search?q=Jaemin%20Lee"> Jaemin Lee</a>, <a href="https://publications.waset.org/abstracts/search?q=Suhong%20Lee"> Suhong Lee</a>, <a href="https://publications.waset.org/abstracts/search?q=Jinyoung%20Chung"> Jinyoung Chung</a>, <a href="https://publications.waset.org/abstracts/search?q=Johoo%20Whang"> Johoo Whang</a> </p> <p class="card-text"><strong>Abstract:</strong></p> The Republic of Korea has been facing strong storage crisis from nuclear waste generation as At Reactor (AR) temporary storage sites are about to reach saturation. Since the country is densely populated with a rate of 491.78 persons per square kilometer, Construction of High-level waste repository will not be a feasible option. In order to tackle the storage waste generation problem which is increasing at a rate of 350 tHM/Yr. and 380 tHM/Yr. in case of 20 PWRs and 4 PHWRs respectively, the study strongly focuses on the advancement of current nuclear power plants to GEN-IV sustainable and ecological nuclear systems by burning TRUs (Pu, MAs). First, Calculations has made to estimate the generation of SNF including Pu and MA from PWR and PHWR NPPS by using the IAEA code Nuclear Fuel Cycle Simulation System (NFCSS) for the period of 2016, 2030 (including the saturation period of each site from 2024~2028), 2089 and 2109 as the number of NPPS will increase due to high import cost of non-nuclear energy sources. 2ndly, in order to produce environmentally sustainable nuclear energy systems, 4 scenarios to burnout the Plutonium and MAs are analyzed with the concentration on burning of MA only, MA and Pu together by utilizing SFR, LFR and KALIMER-600 burner reactor after recycling the spent oxide fuel from PWR through pyro processing technology developed by Korea Atomic Energy Research Institute (KAERI) which shows promising and sustainable future benefits by minimizing the HLW generation with regard to waste amount, decay heat, and activity. Finally, With the concentration on front and back end fuel cycles for open and closed fuel cycles of PWR and Pyro-SFR respectively, an overall assessment has been made which evaluates the quantitative as well as economical combativeness of SFR metallic fuel against PWR once through nuclear fuel cycle. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=GEN%20IV%20nuclear%20fuel%20cycle" title="GEN IV nuclear fuel cycle">GEN IV nuclear fuel cycle</a>, <a href="https://publications.waset.org/abstracts/search?q=nuclear%20waste" title=" nuclear waste"> nuclear waste</a>, <a href="https://publications.waset.org/abstracts/search?q=waste%20sustainability" title=" waste sustainability"> waste sustainability</a>, <a href="https://publications.waset.org/abstracts/search?q=transmutation" title=" transmutation"> transmutation</a> </p> <a href="https://publications.waset.org/abstracts/58570/development-of-scenarios-for-sustainable-next-generation-nuclear-system" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/58570.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">352</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2836</span> Study of Temperature Distribution in Coolant Channel of Nuclear Power with Fuel Cylinder Element Using Fluent Software</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Elham%20Zamiri">Elham Zamiri</a> </p> <p class="card-text"><strong>Abstract:</strong></p> In this research, we have focused on numeral simulation of a fuel rod in order to examine distribution of heat temperature in components of fuel rod by Fluent software by providing steady state, single phase fluid flow, frequency heat flux in a fuel rod in nuclear reactor to numeral simulation. Results of examining different layers of a fuel rod consist of fuel layer, gap, pod, and fluid cooling flow, also examining thermal properties and fluids such as heat transition rate and pressure drop. The obtained results through analytical method and results of other sources have been compared and have appropriate correspondence. Results show that using heavy water as cooling fluid along with few layers of gas and pod have the ability of reducing the temperature from above 300 <sup>◦</sup>C to 70 <sup>◦</sup>C. This investigation is developable for any geometry and material used in the nuclear reactor. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=nuclear%20fuel%20fission" title="nuclear fuel fission">nuclear fuel fission</a>, <a href="https://publications.waset.org/abstracts/search?q=numberal%20simulation" title=" numberal simulation"> numberal simulation</a>, <a href="https://publications.waset.org/abstracts/search?q=fuel%20rod" title=" fuel rod"> fuel rod</a>, <a href="https://publications.waset.org/abstracts/search?q=reactor" title=" reactor"> reactor</a>, <a href="https://publications.waset.org/abstracts/search?q=Fluent%20software" title=" Fluent software"> Fluent software</a> </p> <a href="https://publications.waset.org/abstracts/108202/study-of-temperature-distribution-in-coolant-channel-of-nuclear-power-with-fuel-cylinder-element-using-fluent-software" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/108202.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">166</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2835</span> Experimental Investigation of Heat Transfer on Vertical Two-Phased Closed Thermosyphon</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=M.%20Hadi%20Kusuma">M. Hadi Kusuma</a>, <a href="https://publications.waset.org/abstracts/search?q=Nandy%20Putra"> Nandy Putra</a>, <a href="https://publications.waset.org/abstracts/search?q=Anhar%20Riza%20Antariksawan"> Anhar Riza Antariksawan</a>, <a href="https://publications.waset.org/abstracts/search?q=Ficky%20Augusta%20Imawan"> Ficky Augusta Imawan</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Heat pipe is considered to be applied as a passive system to remove residual heat that generated from reactor core when incident occur or from spent fuel storage pool. The objectives are to characterized the heat transfer phenomena, performance of heat pipe, and as a model for large heat pipe will be applied as passive cooling system on nuclear spent fuel pool storage. In this experimental wickless heat pipe or two-phase closed thermosyphon (TPCT) is used. Variation of heat flux are 611.24 Watt/m<sup>2</sup> - 3291.29 Watt/m<sup>2</sup>. Variation of filling ratio are 45 - 70%. Variation of initial pressure are -62 to -74 cm Hg. Demineralized water is used as working fluid in the TPCT. The results showed that increasing of heat load leads to an increase of evaporation of the working fluid. The optimum filling ratio obtained for 60% of TPCT evaporator volume, and initial pressure variation gave different TPCT wall temperature characteristic. TPCT showed best performance with 60% filling ratio and can be consider to be applied as passive residual heat removal system or passive cooling system on spent fuel storage pool. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=two-phase%20closed%20term%20syphon" title="two-phase closed term syphon">two-phase closed term syphon</a>, <a href="https://publications.waset.org/abstracts/search?q=heat%20pipe" title=" heat pipe"> heat pipe</a>, <a href="https://publications.waset.org/abstracts/search?q=passive%20cooling" title=" passive cooling"> passive cooling</a>, <a href="https://publications.waset.org/abstracts/search?q=spent%20fuel%20storage%20pool" title=" spent fuel storage pool"> spent fuel storage pool</a> </p> <a href="https://publications.waset.org/abstracts/30599/experimental-investigation-of-heat-transfer-on-vertical-two-phased-closed-thermosyphon" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/30599.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">330</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2834</span> Implications of Fuel Reloading in Heterogeneous Thorium-Based Fuel Designs for Improved Fuel Cycle Characteristics</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Hendrik%20Bernard%20Van%20Der%20Walt">Hendrik Bernard Van Der Walt</a>, <a href="https://publications.waset.org/abstracts/search?q=Frik%20Van%20Niekerk"> Frik Van Niekerk</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Fuel models render a reduction in BOL when thorium is added to a reactor core. Thorium emulates the role of a fertile poison, and is beneficial for reducing beginning of cycle (BOC) excess reactivity. In spite of the build-up of 233U over the duration of a fuel cycle, the effects of fuel reloading have a significant impact on fuel viability, especially in the case of heterogeneous thorium-based fuels. The most common practice of compensating for the reduction of BOC reactivity is the addition of fissile isotopes (uranium fuel with increased enrichment or plutonium). This study introduces a heterogeneous thorium-based fuel with minimal fissile isotope additions. A pseudo reloading scheme was developed for numerical simulations of an infinite reactor based on the North-Anna 1 reactor operating in Virginia, USA. Use of this reloading pattern allows new thorium-based fuel to be loaded into the reactor model as part of a phasing in strategy at the end of any conventional reactor cycle. Results demonstrate the effects of thorium-based fuel on fuel cycle characteristics such as fuel cycle length, neutron economy and material matrix. Application of the above mentioned approach delivered promising results and presents a heterogeneous thorium-based fuel which could replace conventional fuel of typical, currently operating (or future) reactors without the need for expensive reactor redesign or fuel recycling strategies. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=nuclear%20fuel" title="nuclear fuel">nuclear fuel</a>, <a href="https://publications.waset.org/abstracts/search?q=nuclear%20characteristics" title=" nuclear characteristics"> nuclear characteristics</a>, <a href="https://publications.waset.org/abstracts/search?q=nuclear%20fuel%20cycle" title=" nuclear fuel cycle"> nuclear fuel cycle</a>, <a href="https://publications.waset.org/abstracts/search?q=thorium-based%20fuel" title=" thorium-based fuel"> thorium-based fuel</a>, <a href="https://publications.waset.org/abstracts/search?q=heterogeneous%20design" title=" heterogeneous design"> heterogeneous design</a>, <a href="https://publications.waset.org/abstracts/search?q=fuel%20reloading" title=" fuel reloading"> fuel reloading</a> </p> <a href="https://publications.waset.org/abstracts/122557/implications-of-fuel-reloading-in-heterogeneous-thorium-based-fuel-designs-for-improved-fuel-cycle-characteristics" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/122557.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">135</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2833</span> Nuclear Characteristics of a Heterogeneous Thorium-Based Fuel Design Aimed at Increasing Fuel Cycle Length of a Typical PWR</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Hendrik%20Bernard%20Van%20Der%20Walt">Hendrik Bernard Van Der Walt</a>, <a href="https://publications.waset.org/abstracts/search?q=Frik%20Van%20Niekerk"> Frik Van Niekerk</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Heterogeneous thorium-based fuels have been proposed as an alternative for conventional reactor fuels and many studies have shown promising results. Fuel cycle characteristics still have to be explored in detail. This study investigates the use of a novel thorium-based fuel design aimed at increasing fuel cycle length of a typical PWR with an explicit focus on thorium- uranium content, neutron spectrum, flux considerations and neutron economy.As nuclear reactions are highly dependent on reactor flux and material matrix, analytical and numerical calculations have been completed to predict the behaviour of the proposed nuclear fuel. The proposed design utilizes various ratios of thorium oxide and uranium oxide pellets within fuel pins, divided into heterogeneous sections of specified length. This design renders multiple regions with unique characteristics. The goal of this study is to determine and optimally utilize these characteristics. Proliferation considerations result in the need for denaturing of heterogeneous regions, which renders more unique characteristics, these aspects were examined in this study. Finally, the use of fertile thorium to emulate a burnable poison for managing excess BOL reactivity has been investigated, as well as an option for flux shaping in a typical PWR. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=nuclear%20fuel" title="nuclear fuel">nuclear fuel</a>, <a href="https://publications.waset.org/abstracts/search?q=nuclear%20characteristics" title=" nuclear characteristics"> nuclear characteristics</a>, <a href="https://publications.waset.org/abstracts/search?q=nuclear%20fuel%20cycle" title=" nuclear fuel cycle"> nuclear fuel cycle</a>, <a href="https://publications.waset.org/abstracts/search?q=thorium-based%20fuel" title=" thorium-based fuel"> thorium-based fuel</a>, <a href="https://publications.waset.org/abstracts/search?q=heterogeneous%20design" title=" heterogeneous design "> heterogeneous design </a> </p> <a href="https://publications.waset.org/abstracts/122551/nuclear-characteristics-of-a-heterogeneous-thorium-based-fuel-design-aimed-at-increasing-fuel-cycle-length-of-a-typical-pwr" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/122551.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">135</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2832</span> Sloshing-Induced Overflow Assessment of the Seismically-Isolated Nuclear Tanks</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Kihyon%20Kwon">Kihyon Kwon</a>, <a href="https://publications.waset.org/abstracts/search?q=Hyun%20T.%20Park"> Hyun T. Park</a>, <a href="https://publications.waset.org/abstracts/search?q=Gil%20Y.%20Chung"> Gil Y. Chung</a>, <a href="https://publications.waset.org/abstracts/search?q=Sang-Hoon%20Lee"> Sang-Hoon Lee</a> </p> <p class="card-text"><strong>Abstract:</strong></p> This paper focuses on assessing sloshing-induced overflow of the seismically-isolated nuclear tanks based on Fluid-Structure Interaction (FSI) analysis. Typically, fluid motion in the seismically-isolated nuclear tank systems may be rather amplified and even overflowed under earthquake. Sloshing-induced overflow in those structures has to be reliably assessed and predicted since it can often cause critical damages to humans and environments. FSI analysis is herein performed to compute the total cumulative overflowed water volume more accurately, by coupling ANSYS with CFX for structural and fluid analyses, respectively. The approach is illustrated on a nuclear liquid storage tank, Spent Fuel Pool (SFP), forgiven conditions under consideration: different liquid levels, Peak Ground Accelerations (PGAs), and post earthquakes. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=FSI%20analysis" title="FSI analysis">FSI analysis</a>, <a href="https://publications.waset.org/abstracts/search?q=seismically-isolated%20nuclear%20tank%20system" title=" seismically-isolated nuclear tank system"> seismically-isolated nuclear tank system</a>, <a href="https://publications.waset.org/abstracts/search?q=sloshing-induced%20overflow" title=" sloshing-induced overflow"> sloshing-induced overflow</a> </p> <a href="https://publications.waset.org/abstracts/7571/sloshing-induced-overflow-assessment-of-the-seismically-isolated-nuclear-tanks" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/7571.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">474</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2831</span> Micro-Cantilever Tests on Hydride Blister and Zirconium Matrix of Zircaloy-4 Cladding Tube</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Ho-A%20Kim">Ho-A Kim</a>, <a href="https://publications.waset.org/abstracts/search?q=Jae-Soo%20Noh"> Jae-Soo Noh</a> </p> <p class="card-text"><strong>Abstract:</strong></p> During reactor operation, hydride blister can occur in spent nuclear fuel (SNF) claddings, and it could worsen the integrity of the claddings locally. Hydride blister can be critical when a pinch-type load is applied in the process of SNF handling and transportation. Micro-cantilever tests were performed to evaluate the risk of local hydride blister by comparing the fracture toughness of local hydride blister and pre-hydrided Zr alloy matrix of SNF cladding on a microscale. Hydride blister was generated by a gaseous charging procedure to simulate an SNF cladding. Micro-cantilevers and pre-cracks were ion-milled with the Ga+ ion beam of FEI Helios 600 at 30kV acceleration voltage. Micro-cantilever tests were conducted using PI 85 pico-indenter (HYSTRON) with for sided conductive diamond flat tip (1 μm x 1 μm) at a speed of 5 nm/sec. The results show that the hydride blister specimen could be fractured in the elastic deformation region, and the fracture toughness of the hydride blister specimen could drop up to 60% of that of the pre-hydrided Zr alloy matrix. Therefore, local hydride blister can degrade the integrity of SNF cladding, and the effect of hydride blister should be taken into account when evaluating failure criteria of claddings during handling, storage, and transportation of SNF. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=fracture%20toughness" title="fracture toughness">fracture toughness</a>, <a href="https://publications.waset.org/abstracts/search?q=hydride%20blister" title=" hydride blister"> hydride blister</a>, <a href="https://publications.waset.org/abstracts/search?q=micro-cantilever%20test" title=" micro-cantilever test"> micro-cantilever test</a>, <a href="https://publications.waset.org/abstracts/search?q=spent%20nuclear%20fuel%20cladding." title=" spent nuclear fuel cladding. "> spent nuclear fuel cladding. </a> </p> <a href="https://publications.waset.org/abstracts/123555/micro-cantilever-tests-on-hydride-blister-and-zirconium-matrix-of-zircaloy-4-cladding-tube" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/123555.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">137</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2830</span> Application of Robotics to Assemble a Used Fuel Container in the Canadian Used Fuel Packing Plant</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Dimitrie%20Marinceu">Dimitrie Marinceu</a> </p> <p class="card-text"><strong>Abstract:</strong></p> The newest Canadian Used Fuel Container (UFC)- (called also “Mark II”) modifies the design approach for its Assembly Robotic Cell (ARC) in the Canadian Used (Nuclear) Fuel Packing Plant (UFPP). Some of the robotic design solutions are presented in this paper. The design indicates that robots and manipulators are expected to be used in the Canadian UFPP. As normally, the UFPP design will incorporate redundancy of all equipment to allow expedient recovery from any postulated upset conditions. Overall, this paper suggests that robot usage will have a significant positive impact on nuclear safety, quality, productivity, and reliability. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=used%20fuel%20packing%20plant" title="used fuel packing plant">used fuel packing plant</a>, <a href="https://publications.waset.org/abstracts/search?q=robotic%20assembly%20cell" title=" robotic assembly cell"> robotic assembly cell</a>, <a href="https://publications.waset.org/abstracts/search?q=used%20fuel%20container" title=" used fuel container"> used fuel container</a>, <a href="https://publications.waset.org/abstracts/search?q=deep%20geological%20repository" title=" deep geological repository"> deep geological repository</a> </p> <a href="https://publications.waset.org/abstracts/56119/application-of-robotics-to-assemble-a-used-fuel-container-in-the-canadian-used-fuel-packing-plant" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/56119.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">291</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2829</span> Nuclear Fuel Safety Threshold Determined by Logistic Regression Plus Uncertainty</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=D.%20S.%20Gomes">D. S. Gomes</a>, <a href="https://publications.waset.org/abstracts/search?q=A.%20T.%20Silva"> A. T. Silva</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Analysis of the uncertainty quantification related to nuclear safety margins applied to the nuclear reactor is an important concept to prevent future radioactive accidents. The nuclear fuel performance code may involve the tolerance level determined by traditional deterministic models producing acceptable results at burn cycles under 62 GWd/MTU. The behavior of nuclear fuel can simulate applying a series of material properties under irradiation and physics models to calculate the safety limits. In this study, theoretical predictions of nuclear fuel failure under transient conditions investigate extended radiation cycles at 75 GWd/MTU, considering the behavior of fuel rods in light-water reactors under reactivity accident conditions. The fuel pellet can melt due to the quick increase of reactivity during a transient. Large power excursions in the reactor are the subject of interest bringing to a treatment that is known as the Fuchs-Hansen model. The point kinetic neutron equations show similar characteristics of non-linear differential equations. In this investigation, the multivariate logistic regression is employed to a probabilistic forecast of fuel failure. A comparison of computational simulation and experimental results was acceptable. The experiments carried out use the pre-irradiated fuels rods subjected to a rapid energy pulse which exhibits the same behavior during a nuclear accident. The propagation of uncertainty utilizes the Wilk's formulation. The variables chosen as essential to failure prediction were the fuel burnup, the applied peak power, the pulse width, the oxidation layer thickness, and the cladding type. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=logistic%20regression" title="logistic regression">logistic regression</a>, <a href="https://publications.waset.org/abstracts/search?q=reactivity-initiated%20accident" title=" reactivity-initiated accident"> reactivity-initiated accident</a>, <a href="https://publications.waset.org/abstracts/search?q=safety%20margins" title=" safety margins"> safety margins</a>, <a href="https://publications.waset.org/abstracts/search?q=uncertainty%20propagation" title=" uncertainty propagation"> uncertainty propagation</a> </p> <a href="https://publications.waset.org/abstracts/65731/nuclear-fuel-safety-threshold-determined-by-logistic-regression-plus-uncertainty" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/65731.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">292</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2828</span> Technical and Economical Evaluation of Electricity Generation and Seawater Desalination Using Nuclear Energy</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=A.%20Hany%20A.%20Khater">A. Hany A. Khater</a>, <a href="https://publications.waset.org/abstracts/search?q=G.%20M.%20Mostafa"> G. M. Mostafa</a>, <a href="https://publications.waset.org/abstracts/search?q=M.%20R.%20Badawy"> M. R. Badawy </a> </p> <p class="card-text"><strong>Abstract:</strong></p> The techno-economic analysis of the nuclear desalination is a very important tool that enables studying of the mutual effects between the nuclear power plant and the coupled desalination plant under different operating conditions, and hence investigating the feasibility of safe and economical production of potable water. For this purpose, a comprehensive model for both technical and economic performance evaluation of the nuclear desalination has been prepared. The developed model has the capability to be used in performing a parametric study for the performance measuring parameters of the nuclear desalination system. Also a sensitivity analysis of varying important factors such as interest/discount rate, power plant availability, fossil fuel prices, purchased electricity price, nuclear fuel cost, and specific base cost for both power and water plant has been conducted. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=uclear%20desalination" title="uclear desalination">uclear desalination</a>, <a href="https://publications.waset.org/abstracts/search?q=PWR" title=" PWR"> PWR</a>, <a href="https://publications.waset.org/abstracts/search?q=MED" title=" MED"> MED</a>, <a href="https://publications.waset.org/abstracts/search?q=MED-TVC" title=" MED-TVC"> MED-TVC</a>, <a href="https://publications.waset.org/abstracts/search?q=MSF" title=" MSF"> MSF</a>, <a href="https://publications.waset.org/abstracts/search?q=RO" title=" RO"> RO</a> </p> <a href="https://publications.waset.org/abstracts/25942/technical-and-economical-evaluation-of-electricity-generation-and-seawater-desalination-using-nuclear-energy" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/25942.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">725</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2827</span> The Use of Nuclear Generation to Provide Power System Stability</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Heather%20Wyman-Pain">Heather Wyman-Pain</a>, <a href="https://publications.waset.org/abstracts/search?q=Yuankai%20Bian"> Yuankai Bian</a>, <a href="https://publications.waset.org/abstracts/search?q=Furong%20Li"> Furong Li</a> </p> <p class="card-text"><strong>Abstract:</strong></p> The decreasing use of fossil fuel power stations has a negative effect on the stability of the electricity systems in many countries. Nuclear power stations have traditionally provided minimal ancillary services to support the system but this must change in the future as they replace fossil fuel generators. This paper explains the development of the four most popular reactor types still in regular operation across the world which have formed the basis for most reactor development since their commercialisation in the 1950s. The use of nuclear power in four countries with varying levels of capacity provided by nuclear generators is investigated, using the primary frequency response provided by generators as a measure for the electricity networks stability, to assess the need for nuclear generators to provide additional support as their share of the generation capacity increases. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=frequency%20control" title="frequency control">frequency control</a>, <a href="https://publications.waset.org/abstracts/search?q=nuclear%20power%20generation" title=" nuclear power generation"> nuclear power generation</a>, <a href="https://publications.waset.org/abstracts/search?q=power%20system%20stability" title=" power system stability"> power system stability</a>, <a href="https://publications.waset.org/abstracts/search?q=system%20inertia" title=" system inertia"> system inertia</a> </p> <a href="https://publications.waset.org/abstracts/47932/the-use-of-nuclear-generation-to-provide-power-system-stability" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/47932.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">437</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2826</span> Consideration of Failed Fuel Detector Location through Computational Flow Dynamics Analysis on Primary Cooling System Flow with Two Outlets</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Sanghoon%20Bae">Sanghoon Bae</a>, <a href="https://publications.waset.org/abstracts/search?q=Hanju%20Cha"> Hanju Cha</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Failed fuel detector (FFD) in research reactor is a very crucial instrument to detect the anomaly from failed fuels in the early stage around primary cooling system (PCS) outlet prior to the decay tank. FFD is considered as a mandatory sensor to ensure the integrity of fuel assemblies and mitigate the consequence from a failed fuel accident. For the effective function of FFD, the location of them should be determined by contemplating the effect from coolant flow around two outlets. For this, the analysis on computational flow dynamics (CFD) should be first performed how the coolant outlet flow including radioactive materials from failed fuels are mixed and discharged through the outlet plenum within certain seconds. The analysis result shows that the outlet flow is well mixed regardless of the position of failed fuel and ultimately illustrates the effect of detector location. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=computational%20flow%20dynamics%20%28CFD%29" title="computational flow dynamics (CFD)">computational flow dynamics (CFD)</a>, <a href="https://publications.waset.org/abstracts/search?q=failed%20fuel%20detector%20%28FFD%29" title=" failed fuel detector (FFD)"> failed fuel detector (FFD)</a>, <a href="https://publications.waset.org/abstracts/search?q=fresh%20fuel%20assembly%20%28FFA%29" title=" fresh fuel assembly (FFA)"> fresh fuel assembly (FFA)</a>, <a href="https://publications.waset.org/abstracts/search?q=spent%20fuel%20assembly%20%28SFA%29" title=" spent fuel assembly (SFA)"> spent fuel assembly (SFA)</a> </p> <a href="https://publications.waset.org/abstracts/73722/consideration-of-failed-fuel-detector-location-through-computational-flow-dynamics-analysis-on-primary-cooling-system-flow-with-two-outlets" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/73722.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">240</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2825</span> Development of DEMO-FNS Hybrid Facility and Its Integration in Russian Nuclear Fuel Cycle</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Yury%20S.%20Shpanskiy">Yury S. Shpanskiy</a>, <a href="https://publications.waset.org/abstracts/search?q=Boris%20V.%20Kuteev"> Boris V. Kuteev</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Development of a fusion-fission hybrid facility based on superconducting conventional tokamak DEMO-FNS runs in Russia since 2013. The main design goal is to reach the technical feasibility and outline prospects of industrial hybrid technologies providing the production of neutrons, fuel nuclides, tritium, high-temperature heat, electricity and subcritical transmutation in Fusion-Fission Hybrid Systems. The facility should operate in a steady-state mode at the fusion power of 40 MW and fission reactions of 400 MW. Major tokamak parameters are the following: major radius R=3.2 m, minor radius a=1.0 m, elongation 2.1, triangularity 0.5. The design provides the neutron wall loading of ~0.2 MW/m², the lifetime neutron fluence of ~2 MWa/m², with the surface area of the active cores and tritium breeding blanket ~100 m². Core plasma modelling showed that the neutron yield ~10¹⁹ n/s is maximal if the tritium/deuterium density ratio is 1.5-2.3. The design of the electromagnetic system (EMS) defined its basic parameters, accounting for the coils strength and stability, and identified the most problematic nodes in the toroidal field coils and the central solenoid. The EMS generates toroidal, poloidal and correcting magnetic fields necessary for the plasma shaping and confinement inside the vacuum vessel. EMC consists of eighteen superconducting toroidal field coils, eight poloidal field coils, five sections of a central solenoid, correction coils, in-vessel coils for vertical plasma control. Supporting structures, the thermal shield, and the cryostat maintain its operation. EMS operates with the pulse duration of up to 5000 hours at the plasma current up to 5 MA. The vacuum vessel (VV) is an all-welded two-layer toroidal shell placed inside the EMS. The free space between the vessel shells is filled with water and boron steel plates, which form the neutron protection of the EMS. The VV-volume is 265 m³, its mass with manifolds is 1800 tons. The nuclear blanket of DEMO-FNS facility was designed to provide functions of minor actinides transmutation, tritium production and enrichment of spent nuclear fuel. The vertical overloading of the subcritical active cores with MA was chosen as prospective. Analysis of the device neutronics and the hybrid blanket thermal-hydraulic characteristics has been performed for the system with functions covering transmutation of minor actinides, production of tritium and enrichment of spent nuclear fuel. A study of FNS facilities role in the Russian closed nuclear fuel cycle was performed. It showed that during ~100 years of operation three FNS facilities with fission power of 3 GW controlled by fusion neutron source with power of 40 MW can burn 98 tons of minor actinides and 198 tons of Pu-239 can be produced for startup loading of 20 fast reactors. Instead of Pu-239, up to 25 kg of tritium per year may be produced for startup of fusion reactors using blocks with lithium orthosilicate instead of fissile breeder blankets. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=fusion-fission%20hybrid%20system" title="fusion-fission hybrid system">fusion-fission hybrid system</a>, <a href="https://publications.waset.org/abstracts/search?q=conventional%20tokamak" title=" conventional tokamak"> conventional tokamak</a>, <a href="https://publications.waset.org/abstracts/search?q=superconducting%20electromagnetic%20system" title=" superconducting electromagnetic system"> superconducting electromagnetic system</a>, <a href="https://publications.waset.org/abstracts/search?q=two-layer%20vacuum%20vessel" title=" two-layer vacuum vessel"> two-layer vacuum vessel</a>, <a href="https://publications.waset.org/abstracts/search?q=subcritical%20active%20cores" title=" subcritical active cores"> subcritical active cores</a>, <a href="https://publications.waset.org/abstracts/search?q=nuclear%20fuel%20cycle" title=" nuclear fuel cycle"> nuclear fuel cycle</a> </p> <a href="https://publications.waset.org/abstracts/107915/development-of-demo-fns-hybrid-facility-and-its-integration-in-russian-nuclear-fuel-cycle" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/107915.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">147</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2824</span> Analysis of Possible Causes of Fukushima Disaster</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Abid%20Hossain%20Khan">Abid Hossain Khan</a>, <a href="https://publications.waset.org/abstracts/search?q=Syam%20Hasan"> Syam Hasan</a>, <a href="https://publications.waset.org/abstracts/search?q=M.%20A.%20R.%20Sarkar"> M. A. R. Sarkar</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Fukushima disaster is one of the most publicly exposed accidents in a nuclear facility which has changed the outlook of people towards nuclear power. Some have used it as an example to establish nuclear energy as an unsafe source, while others have tried to find the real reasons behind this accident. Many papers have tried to shed light on the possible causes, some of which are purely based on assumptions while others rely on rigorous data analysis. To our best knowledge, none of the works can say with absolute certainty that there is a single prominent reason that has paved the way to this unexpected incident. This paper attempts to compile all the apparent reasons behind Fukushima disaster and tries to analyze and identify the most likely one. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=fuel%20meltdown" title="fuel meltdown">fuel meltdown</a>, <a href="https://publications.waset.org/abstracts/search?q=Fukushima%20disaster" title=" Fukushima disaster"> Fukushima disaster</a>, <a href="https://publications.waset.org/abstracts/search?q=Manmade%20calamity" title=" Manmade calamity"> Manmade calamity</a>, <a href="https://publications.waset.org/abstracts/search?q=nuclear%20facility" title=" nuclear facility"> nuclear facility</a>, <a href="https://publications.waset.org/abstracts/search?q=tsunami" title=" tsunami"> tsunami</a> </p> <a href="https://publications.waset.org/abstracts/88370/analysis-of-possible-causes-of-fukushima-disaster" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/88370.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">266</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2823</span> Refining Waste Spent Hydroprocessing Catalyst and Their Metal Recovery</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Meena%20Marafi">Meena Marafi</a>, <a href="https://publications.waset.org/abstracts/search?q=Mohan%20S.%20Rana"> Mohan S. Rana</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Catalysts play an important role in producing valuable fuel products in petroleum refining; but, due to feedstock’s impurities catalyst gets deactivated with carbon and metal deposition. The disposal of spent catalyst falls under the category of hazardous industrial waste that requires strict agreement with environmental regulations. The spent hydroprocessing catalyst contains Mo, V and Ni at high concentrations that have been found to be economically significant for recovery. Metal recovery process includes deoiling, decoking, grinding, dissolving and treatment with complexing leaching agent such as ethylene diamine tetra acetic acid (EDTA). The process conditions have been optimized as a function of time, temperature and EDTA concentration in presence of ultrasonic agitation. The results indicated that optimum condition established through this approach could recover 97%, 94% and 95% of the extracted Mo, V and Ni, respectively, while 95% EDTA was recovered after acid treatment. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=atmospheric%20residue%20desulfurization%20%28ARDS%29" title="atmospheric residue desulfurization (ARDS)">atmospheric residue desulfurization (ARDS)</a>, <a href="https://publications.waset.org/abstracts/search?q=deactivation" title=" deactivation"> deactivation</a>, <a href="https://publications.waset.org/abstracts/search?q=hydrotreating" title=" hydrotreating"> hydrotreating</a>, <a href="https://publications.waset.org/abstracts/search?q=spent%20catalyst" title=" spent catalyst"> spent catalyst</a> </p> <a href="https://publications.waset.org/abstracts/72632/refining-waste-spent-hydroprocessing-catalyst-and-their-metal-recovery" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/72632.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">323</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2822</span> Finite Element Analysis of the Blanking and Stamping Processes of Nuclear Fuel Spacer Grids</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Rafael%20Oliveira%20Santos">Rafael Oliveira Santos</a>, <a href="https://publications.waset.org/abstracts/search?q=Luciano%20Pessanha%20Moreira"> Luciano Pessanha Moreira</a>, <a href="https://publications.waset.org/abstracts/search?q=Marcelo%20Costa%20Cardoso"> Marcelo Costa Cardoso</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Spacer grid assembly supporting the nuclear fuel rods is an important concern in the design of structural components of a Pressurized Water Reactor (PWR). The spacer grid is composed by springs and dimples which are formed from a strip sheet by means of blanking and stamping processes. In this paper, the blanking process and tooling parameters are evaluated by means of a 2D plane-strain finite element model in order to evaluate the punch load and quality of the sheared edges of Inconel 718 strips used for nuclear spacer grids. A 3D finite element model is also proposed to predict the tooling loads resulting from the stamping process of a preformed Inconel 718 strip and to analyse the residual stress effects upon the spring and dimple design geometries of a nuclear spacer grid. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=blanking%20process" title="blanking process">blanking process</a>, <a href="https://publications.waset.org/abstracts/search?q=damage%20model" title=" damage model"> damage model</a>, <a href="https://publications.waset.org/abstracts/search?q=finite%20element%20modelling" title=" finite element modelling"> finite element modelling</a>, <a href="https://publications.waset.org/abstracts/search?q=inconel%20718" title=" inconel 718"> inconel 718</a>, <a href="https://publications.waset.org/abstracts/search?q=spacer%20grids" title=" spacer grids"> spacer grids</a>, <a href="https://publications.waset.org/abstracts/search?q=stamping%20process" title=" stamping process"> stamping process</a> </p> <a href="https://publications.waset.org/abstracts/35882/finite-element-analysis-of-the-blanking-and-stamping-processes-of-nuclear-fuel-spacer-grids" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/35882.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">344</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2821</span> TRACE/FRAPTRAN Analysis of Kuosheng Nuclear Power Plant Dry-Storage System</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=J.%20R.%20Wang">J. R. Wang</a>, <a href="https://publications.waset.org/abstracts/search?q=Y.%20Chiang"> Y. Chiang</a>, <a href="https://publications.waset.org/abstracts/search?q=W.%20Y.%20Li"> W. Y. Li</a>, <a href="https://publications.waset.org/abstracts/search?q=H.%20T.%20Lin"> H. T. Lin</a>, <a href="https://publications.waset.org/abstracts/search?q=H.%20C.%20Chen"> H. C. Chen</a>, <a href="https://publications.waset.org/abstracts/search?q=C.%20Shih"> C. Shih</a>, <a href="https://publications.waset.org/abstracts/search?q=S.%20W.%20Chen"> S. W. Chen</a> </p> <p class="card-text"><strong>Abstract:</strong></p> The dry-storage systems of nuclear power plants (NPPs) in Taiwan have become one of the major safety concerns. There are two steps considered in this study. The first step is the verification of the TRACE by using VSC-17 experimental data. The results of TRACE were similar to the VSC-17 data. It indicates that TRACE has the respectable accuracy in the simulation and analysis of the dry-storage systems. The next step is the application of TRACE in the dry-storage system of Kuosheng NPP (BWR/6). Kuosheng NPP is the second BWR NPP of Taiwan Power Company. In order to solve the storage of the spent fuels, Taiwan Power Company developed the new dry-storage system for Kuosheng NPP. In this step, the dry-storage system model of Kuosheng NPP was established by TRACE. Then, the steady state simulation of this model was performed and the results of TRACE were compared with the Kuosheng NPP data. Finally, this model was used to perform the safety analysis of Kuosheng NPP dry-storage system. Besides, FRAPTRAN was used tocalculate the transient performance of fuel rods. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=BWR" title="BWR">BWR</a>, <a href="https://publications.waset.org/abstracts/search?q=TRACE" title=" TRACE"> TRACE</a>, <a href="https://publications.waset.org/abstracts/search?q=FRAPTRAN" title=" FRAPTRAN"> FRAPTRAN</a>, <a href="https://publications.waset.org/abstracts/search?q=dry-storage" title=" dry-storage"> dry-storage</a> </p> <a href="https://publications.waset.org/abstracts/12388/tracefraptran-analysis-of-kuosheng-nuclear-power-plant-dry-storage-system" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/12388.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">519</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2820</span> Investigation of Minor Actinide-Contained Thorium Fuel Impacts on CANDU-Type Reactor Neutronics Using Computational Method </h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=S.%20A.%20H.%20Feghhi">S. A. H. Feghhi</a>, <a href="https://publications.waset.org/abstracts/search?q=Z.%20Gholamzadeh"> Z. Gholamzadeh</a>, <a href="https://publications.waset.org/abstracts/search?q=Z.%20Alipoor"> Z. Alipoor</a>, <a href="https://publications.waset.org/abstracts/search?q=C.%20Tenreiro"> C. Tenreiro </a> </p> <p class="card-text"><strong>Abstract:</strong></p> Currently, thorium fuel has been especially noticed because of its proliferation resistance than long half-life alpha emitter minor actinides, breeding capability in fast and thermal neutron flux and mono-isotopic naturally abundant. In recent years, efficiency of minor actinide burning up in PWRs has been investigated. Hence, a minor actinide-contained thorium based fuel matrix can confront both proliferation resistance and nuclear waste depletion aims. In the present work, minor actinide depletion rate in a CANDU-type nuclear core modeled using MCNP code has been investigated. The obtained effects of minor actinide load as mixture of thorium fuel matrix on the core neutronics has been studiedwith comparingpresence and non-presence of minor actinide component in the fuel matrix.Depletion rate of minor actinides in the MA-contained fuel has been calculated using different power loads.According to the obtained computational data, minor actinide loading in the modeled core results in more negative reactivity coefficients. The MA-contained fuel achieves less radial peaking factor in the modeled core. The obtained computational results showed 140 kg of 464 kg initial load of minor actinide has been depleted in during a 6-year burn up in 10 MW power. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=minor%20actinide%20burning" title="minor actinide burning">minor actinide burning</a>, <a href="https://publications.waset.org/abstracts/search?q=CANDU-type%20reactor" title=" CANDU-type reactor"> CANDU-type reactor</a>, <a href="https://publications.waset.org/abstracts/search?q=MCNPX%20code" title=" MCNPX code"> MCNPX code</a>, <a href="https://publications.waset.org/abstracts/search?q=neutronic%20parameters" title=" neutronic parameters "> neutronic parameters </a> </p> <a href="https://publications.waset.org/abstracts/13951/investigation-of-minor-actinide-contained-thorium-fuel-impacts-on-candu-type-reactor-neutronics-using-computational-method" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/13951.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">457</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2819</span> Comparision of Bioleaching of Metals from Spent Petroleum Catalyst Using Acidithiobacillus Ferrooxidans and Acidthiobacillus Thiooxidans</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Haragobinda%20Srichandan">Haragobinda Srichandan</a>, <a href="https://publications.waset.org/abstracts/search?q=Ashish%20Pathak"> Ashish Pathak</a>, <a href="https://publications.waset.org/abstracts/search?q=Dong%20Jin%20Kim"> Dong Jin Kim</a>, <a href="https://publications.waset.org/abstracts/search?q=Seoung-Won%20Lee"> Seoung-Won Lee</a> </p> <p class="card-text"><strong>Abstract:</strong></p> The present investigation deals with bioleaching of spent petroleum catalyst using At. ferrooxidans and At. thiooxidans. The spent catalyst used in the present study was pretreated with acetone to remove the oily hydrocarbons. FESEM and XPS analysis indicated the presence of metals in sulfide and oxide forms in spent catalyst. Both At. ferrooxidans and At. thiooxidans were found to be highly effective in producing the acid. Bioleaching with At. ferrooxidans and At. thiooxidans led to higher recovery of metals compare to control. During bioleaching similar recoveries of metals were obtained using At. ferrooxidans and At. thiooxidans. This might be due to the presence of metals as soluble oxides and sulphides in the spent catalyst. At the end of bioleaching, about 87-90% Ni, 34% Al, 65-73% Mo and 92-97% V were leached using above bacteria. It is elucidated that bioleaching with At. thiooxidans is comparatively more advantageous due to lower cost of sulphur. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=At.%20ferrooxidans" title="At. ferrooxidans">At. ferrooxidans</a>, <a href="https://publications.waset.org/abstracts/search?q=bioleaching" title=" bioleaching"> bioleaching</a>, <a href="https://publications.waset.org/abstracts/search?q=metal%20recovery" title=" metal recovery"> metal recovery</a>, <a href="https://publications.waset.org/abstracts/search?q=spent%20catalyst" title=" spent catalyst"> spent catalyst</a> </p> <a href="https://publications.waset.org/abstracts/1872/comparision-of-bioleaching-of-metals-from-spent-petroleum-catalyst-using-acidithiobacillus-ferrooxidans-and-acidthiobacillus-thiooxidans" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/1872.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">292</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2818</span> Fuel Inventory/ Depletion Analysis for a Thorium-Uranium Dioxide (Th-U) O2 Pin Cell Benchmark Using Monte Carlo and Deterministic Codes with New Version VIII.0 of the Evaluated Nuclear Data File (ENDF/B) Nuclear Data Library</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Jamal%20Al-Zain">Jamal Al-Zain</a>, <a href="https://publications.waset.org/abstracts/search?q=O.%20El%20Hajjaji"> O. El Hajjaji</a>, <a href="https://publications.waset.org/abstracts/search?q=T.%20El%20Bardouni"> T. El Bardouni</a> </p> <p class="card-text"><strong>Abstract:</strong></p> A (Th-U) O2 fuel pin benchmark made up of 25 w/o U and 75 w/o Th was used. In order to analyze the depletion and inventory of the fuel for the pressurized water reactor pin-cell model. The new version VIII.0 of the ENDF/B nuclear data library was used to create a data set in ACE format at various temperatures and process the data using the MAKXSF6.2 and NJOY2016 programs to process the data at the various temperatures in order to conduct this study and analyze cross-section data. The infinite multiplication factor, the concentrations and activities of the main fission products, the actinide radionuclides accumulated in the pin cell, and the total radioactivity were all estimated and compared in this study using the Monte Carlo N-Particle 6 (MCNP6.2) and DRAGON5 programs. Additionally, the behavior of the Pressurized Water Reactor (PWR) thorium pin cell that is dependent on burn-up (BU) was validated and compared with the reference data obtained using the Massachusetts Institute of Technology (MIT-MOCUP), Idaho National Engineering and Environmental Laboratory (INEEL-MOCUP), and CASMO-4 codes. The results of this study indicate that all of the codes examined have good agreements. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=PWR%20thorium%20pin%20cell" title="PWR thorium pin cell">PWR thorium pin cell</a>, <a href="https://publications.waset.org/abstracts/search?q=ENDF%2FB-VIII.0" title=" ENDF/B-VIII.0"> ENDF/B-VIII.0</a>, <a href="https://publications.waset.org/abstracts/search?q=MAKXSF6.2" title=" MAKXSF6.2"> MAKXSF6.2</a>, <a href="https://publications.waset.org/abstracts/search?q=NJOY2016" title=" NJOY2016"> NJOY2016</a>, <a href="https://publications.waset.org/abstracts/search?q=MCNP6.2" title=" MCNP6.2"> MCNP6.2</a>, <a href="https://publications.waset.org/abstracts/search?q=DRAGON5" title=" DRAGON5"> DRAGON5</a>, <a href="https://publications.waset.org/abstracts/search?q=fuel%20burn-up." title=" fuel burn-up."> fuel burn-up.</a> </p> <a href="https://publications.waset.org/abstracts/168660/fuel-inventory-depletion-analysis-for-a-thorium-uranium-dioxide-th-u-o2-pin-cell-benchmark-using-monte-carlo-and-deterministic-codes-with-new-version-viii0-of-the-evaluated-nuclear-data-file-endfb-nuclear-data-library" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/168660.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">103</span> </span> </div> </div> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">2817</span> Improvements in Transient Testing in The Transient REActor Test (TREAT) with a Choice of Filter</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Harish%20Aryal">Harish Aryal</a> </p> <p class="card-text"><strong>Abstract:</strong></p> The safe and reliable operation of nuclear reactors has always been one of the topmost priorities in the nuclear industry. Transient testing allows us to understand the time-dependent behavior of the neutron population in response to either a planned change in the reactor conditions or unplanned circumstances. These unforeseen conditions might occur due to sudden reactivity insertions, feedback, power excursions, instabilities, and accidents. To study such behavior, we need transient testing, which is like car crash testing, to estimate the durability and strength of a car design. In nuclear designs, such transient testing can simulate a wide range of accidents due to sudden reactivity insertions and helps to study the feasibility and integrity of the fuel to be used in certain reactor types. This testing involves a high neutron flux environment and real-time imaging technology with advanced instrumentation with appropriate accuracy and resolution to study the fuel slumping behavior. With the aid of transient testing and adequate imaging tools, it is possible to test the safety basis for reactor and fuel designs that serves as a gateway in licensing advanced reactors in the future. To that end, it is crucial to fully understand advanced imaging techniques both analytically and via simulations. This paper presents an innovative method of supporting real-time imaging of fuel pins and other structures during transient testing. The major fuel-motion detection device that is studied in this dissertation is the Hodoscope which requires collimators. This paper provides 1) an MCNP model and simulation of a Transient Reactor Test (TREAT) core with a central fuel element replaced by a slotted fuel element that provides an open path between test samples and a hodoscope detector and 2) a choice of good filter to improve image resolution. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=hodoscope" title="hodoscope">hodoscope</a>, <a href="https://publications.waset.org/abstracts/search?q=transient%20testing" title=" transient testing"> transient testing</a>, <a href="https://publications.waset.org/abstracts/search?q=collimators" title=" collimators"> collimators</a>, <a href="https://publications.waset.org/abstracts/search?q=MCNP" title=" MCNP"> MCNP</a>, <a href="https://publications.waset.org/abstracts/search?q=TREAT" title=" TREAT"> TREAT</a>, <a href="https://publications.waset.org/abstracts/search?q=hodogram" title=" hodogram"> hodogram</a>, <a href="https://publications.waset.org/abstracts/search?q=filters" title=" filters"> filters</a> </p> <a href="https://publications.waset.org/abstracts/167624/improvements-in-transient-testing-in-the-transient-reactor-test-treat-with-a-choice-of-filter" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/167624.pdf" target="_blank" class="btn btn-primary btn-sm">PDF</a> <span class="bg-info text-light px-1 py-1 float-right rounded"> Downloads <span class="badge badge-light">77</span> </span> </div> </div> <ul class="pagination"> <li class="page-item disabled"><span class="page-link">&lsaquo;</span></li> <li class="page-item active"><span class="page-link">1</span></li> <li class="page-item"><a class="page-link" href="https://publications.waset.org/abstracts/search?q=spent%20nuclear%20fuel&page=2">2</a></li> <li class="page-item"><a class="page-link" href="https://publications.waset.org/abstracts/search?q=spent%20nuclear%20fuel&page=3">3</a></li> 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