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Kuosheng</title> <meta name="description" content="Search results for: Kuosheng"> <meta name="keywords" content="Kuosheng"> <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 navbar-toggler ml-auto" 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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="Kuosheng"> <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> 11</div> </div> </div> </div> <h1 class="mt-3 mb-3 text-center" style="font-size:1.6rem;">Search results for: Kuosheng</h1> <div class="card paper-listing mb-3 mt-3"> <h5 class="card-header" style="font-size:.9rem"><span class="badge badge-info">11</span> The Establishment and Application of TRACE/FRAPTRAN Model for Kuosheng Nuclear Power Plant </h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <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=W.%20K.%20Lin"> W. K. Lin</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=H.%20T.%20Lin"> H. T. Lin</a>, <a href="https://publications.waset.org/abstracts/search?q=H.%20C.%20Chang"> H. C. Chang</a>, <a href="https://publications.waset.org/abstracts/search?q=W.%20Y.%20Li"> W. Y. Li</a> </p> <p class="card-text"><strong>Abstract:</strong></p> Kuosheng nuclear power plant (NPP) is a BWR/6 type NPP and located on the northern coast of Taiwan. First, Kuosheng NPP TRACE model were developed in this research. In order to assess the system response of Kuosheng NPP TRACE model, startup tests data were used to evaluate Kuosheng NPP TRACE model. Second, the over pressurization transient analysis of Kuosheng NPP TRACE model was performed. Besides, in order to confirm the mechanical property and integrity of fuel rods, FRAPTRAN analysis was also performed in this study. <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=safety%20analysis" title=" safety analysis"> safety analysis</a>, <a href="https://publications.waset.org/abstracts/search?q=BWR%2F6" title=" BWR/6"> BWR/6</a>, <a href="https://publications.waset.org/abstracts/search?q=FRAPTRA" title=" FRAPTRA"> FRAPTRA</a> </p> <a href="https://publications.waset.org/abstracts/18370/the-establishment-and-application-of-tracefraptran-model-for-kuosheng-nuclear-power-plant" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/18370.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">563</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">10</span> The SBO/LOCA Analysis of TRACE/SNAP for Kuosheng Nuclear Power Plant</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.%20Chiang"> Y. Chiang</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> </p> <p class="card-text"><strong>Abstract:</strong></p> Kuosheng Nuclear Power Plant (NPP) is located on the northern coast of Taiwan. Its nuclear steam supply system is a type of BWR/6 designed and built by General Electric on a twin unit concept. First, the methodology of Kuosheng NPP SPU (Stretch Power Uprate) safety analysis TRACE/SNAP model was developed in this research. Then, in order to estimate the safety of Kuosheng NPP under the more severe condition, the SBO (Station Blackout) + LOCA (Loss-of-Coolant Accident) transient analysis of Kuosheng NPP SPU TRACE/SNAP model was performed. Besides, the animation model of Kuosheng NPP was presented using the animation function of SNAP with TRACE/SNAP analysis results. <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=safety%20analysis" title=" safety analysis"> safety analysis</a>, <a href="https://publications.waset.org/abstracts/search?q=BWR%2F6" title=" BWR/6"> BWR/6</a>, <a href="https://publications.waset.org/abstracts/search?q=severe%20accident" title=" severe accident"> severe accident</a> </p> <a href="https://publications.waset.org/abstracts/12387/the-sboloca-analysis-of-tracesnap-for-kuosheng-nuclear-power-plant" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/12387.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">714</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">9</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">8</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">7</span> The Establishment of RELAP5/SNAP Model for Kuosheng Nuclear Power Plant </h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=C.%20Shih">C. Shih</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=H.%20C.%20Chang"> H. C. Chang</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=S.%20C.%20Chiang"> S. C. Chiang</a>, <a href="https://publications.waset.org/abstracts/search?q=T.%20Y.%20Yu"> T. Y. Yu </a> </p> <p class="card-text"><strong>Abstract:</strong></p> After the measurement uncertainty recapture (MUR) power uprates, Kuosheng nuclear power plant (NPP) was uprated the power from 2894 MWt to 2943 MWt. For power upgrade, several codes (e.g., TRACE, RELAP5, etc.) were applied to assess the safety of Kuosheng NPP. Hence, the main work of this research is to establish a RELAP5/MOD3.3 model of Kuosheng NPP with SNAP interface. The establishment of RELAP5/SNAP model was referred to the FSAR, training documents, and TRACE model which has been developed and verified before. After completing the model establishment, the startup test scenarios would be applied to the RELAP5/SNAP model. With comparing the startup test data and TRACE analysis results, the applicability of RELAP5/SNAP model would be assessed. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=RELAP5" title="RELAP5">RELAP5</a>, <a href="https://publications.waset.org/abstracts/search?q=TRACE" title=" TRACE"> TRACE</a>, <a href="https://publications.waset.org/abstracts/search?q=SNAP" title=" SNAP"> SNAP</a>, <a href="https://publications.waset.org/abstracts/search?q=BWR" title=" BWR"> BWR</a> </p> <a href="https://publications.waset.org/abstracts/56347/the-establishment-of-relap5snap-model-for-kuosheng-nuclear-power-plant" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/56347.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">429</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">6</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">5</span> Using HABIT to Estimate the Concentration of CO2 and H2SO4 for Kuosheng Nuclear Power Plant</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=W.%20Y.%20Li"> W. Y. Li</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=S.%20W.%20Chen"> S. W. Chen</a>, <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=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> </p> <p class="card-text"><strong>Abstract:</strong></p> In this research, the HABIT code was used to estimate the concentration under the CO<sub>2</sub> and H<sub>2</sub>SO<sub>4</sub> storage burst conditions for Kuosheng nuclear power plant (NPP). The Final Safety Analysis Report (FSAR) and reports were used in this research. In addition, to evaluate the control room habitability for these cases, the HABIT analysis results were compared with the R.G. 1.78 failure criteria. The comparison results show that the HABIT results are below the criteria. Additionally, some sensitivity studies (stability classification, wind speed and control room intake rate) were performed in this study. <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=HABIT" title=" HABIT"> HABIT</a>, <a href="https://publications.waset.org/abstracts/search?q=habitability" title=" habitability"> habitability</a>, <a href="https://publications.waset.org/abstracts/search?q=Kuosheng" title=" Kuosheng"> Kuosheng</a> </p> <a href="https://publications.waset.org/abstracts/83491/using-habit-to-estimate-the-concentration-of-co2-and-h2so4-for-kuosheng-nuclear-power-plant" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/83491.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">489</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">4</span> The Study of Ultimate Response Guideline of Kuosheng BWR/6 Nuclear Power Plant Using TRACE and SNAP</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=J.%20H.%20Yang"> J. H. Yang</a>, <a href="https://publications.waset.org/abstracts/search?q=Y.%20Chiang"> Y. Chiang</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>, <a href="https://publications.waset.org/abstracts/search?q=S.%20C.%20Chiang"> S. C. Chiang</a>, <a href="https://publications.waset.org/abstracts/search?q=T.%20Y.%20Yu"> T. Y. Yu</a> </p> <p class="card-text"><strong>Abstract:</strong></p> In this study of ultimate response guideline (URG), Kuosheng BWR/6 nuclear power plant (NPP) TRACE model was established. The reactor depressurization, low pressure water injection, and containment venting are the main actions of URG. This research focuses to evaluate the efficiency of URG under Fukushima-like conditions. Additionally, the sensitivity study of URG was also performed in this research. The analysis results of TRACE present that URG can keep the peak cladding temperature (PCT) below 1088.7 K (the failure criteria) under Fukushima-like conditions. It implied that Kuosheng NPP was at the safe situation. <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=safety%20analysis" title=" safety analysis"> safety analysis</a>, <a href="https://publications.waset.org/abstracts/search?q=ultimate%20response%20guideline%20%28URG%29" title=" ultimate response guideline (URG)"> ultimate response guideline (URG)</a> </p> <a href="https://publications.waset.org/abstracts/67256/the-study-of-ultimate-response-guideline-of-kuosheng-bwr6-nuclear-power-plant-using-trace-and-snap" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/67256.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">562</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">3</span> The Concentration Analysis of CO2 Using ALOHA Code for Kuosheng Nuclear Power Plant</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=H.%20C.%20Chen"> H. C. Chen</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=S.%20W.%20Chen"> S. W. Chen</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=C.%20Shih"> C. Shih </a> </p> <p class="card-text"><strong>Abstract:</strong></p> Not only radiation materials, but also the normal chemical material stored in the power plant can cause a risk to the residents. In this research, the ALOHA code was used to perform the concentration analysis under the CO<sub>2</sub> storage burst or leakage conditions for Kuosheng nuclear power plant (NPP). The Final Safety Analysis Report (FSAR) and data were used in this study. Additionally, the analysis results of ALOHA code were compared with the R.G. 1.78 failure criteria in order to confirm the control room habitability. The comparison results show that the ALOHA result for burst case was 0.923 g/m<sup>3</sup> which was below the criteria. However, the ALOHA results for leakage case was 11.3 g/m<sup>3</sup>. <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=ALOHA" title=" ALOHA"> ALOHA</a>, <a href="https://publications.waset.org/abstracts/search?q=habitability" title=" habitability"> habitability</a>, <a href="https://publications.waset.org/abstracts/search?q=Kuosheng" title=" Kuosheng"> Kuosheng</a> </p> <a href="https://publications.waset.org/abstracts/89156/the-concentration-analysis-of-co2-using-aloha-code-for-kuosheng-nuclear-power-plant" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/89156.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">2</span> Dose Evaluations with SNAP/RADTRAD for Loss of Coolant Accidents in a BWR6 Nuclear Power Plant</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Kai%20Chun%20Yang">Kai Chun Yang</a>, <a href="https://publications.waset.org/abstracts/search?q=Shao-Wen%20Chen"> Shao-Wen Chen</a>, <a href="https://publications.waset.org/abstracts/search?q=Jong-Rong%20Wang"> Jong-Rong Wang</a>, <a href="https://publications.waset.org/abstracts/search?q=Chunkuan%20Shih"> Chunkuan Shih</a>, <a href="https://publications.waset.org/abstracts/search?q=Jung-Hua%20Yang"> Jung-Hua Yang</a>, <a href="https://publications.waset.org/abstracts/search?q=Hsiung-Chih%20Chen"> Hsiung-Chih Chen</a>, <a href="https://publications.waset.org/abstracts/search?q=Wen-Sheng%20Hsu"> Wen-Sheng Hsu</a> </p> <p class="card-text"><strong>Abstract:</strong></p> In this study, we build RADionuclide Transport, Removal And Dose Estimation/Symbolic Nuclear Analysis Package (SNAP/RADTRAD) model of Kuosheng Nuclear Power Plant which is based on the Final Safety Evaluation Report (FSAR) and other data of Kuosheng Nuclear Power Plant. It is used to estimate the radiation dose of the Exclusion Area Boundary (EAB), the Low Population Zone (LPZ), and the control room following ‘release from the containment’ case in Loss Of Coolant Accident (LOCA). The RADTRAD analysis result shows that the evaluation dose at EAB, LPZ, and the control room are close to the FSAR data, and all of the doses are lower than the regulatory limits. At last, we do a sensitivity analysis and observe that the evaluation doses increase as the intake rate of the control room increases. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=RADTRAD" title="RADTRAD">RADTRAD</a>, <a href="https://publications.waset.org/abstracts/search?q=radionuclide%20transport" title=" radionuclide transport"> radionuclide transport</a>, <a href="https://publications.waset.org/abstracts/search?q=removal%20and%20dose%20estimation" title=" removal and dose estimation"> removal and dose estimation</a>, <a href="https://publications.waset.org/abstracts/search?q=snap" title=" snap"> snap</a>, <a href="https://publications.waset.org/abstracts/search?q=symbolic%20nuclear%20analysis%20package" title=" symbolic nuclear analysis package"> symbolic nuclear analysis package</a>, <a href="https://publications.waset.org/abstracts/search?q=boiling%20water%20reactor" title=" boiling water reactor"> boiling water reactor</a>, <a href="https://publications.waset.org/abstracts/search?q=NPP" title=" NPP"> NPP</a>, <a href="https://publications.waset.org/abstracts/search?q=kuosheng" title=" kuosheng"> kuosheng</a> </p> <a href="https://publications.waset.org/abstracts/92352/dose-evaluations-with-snapradtrad-for-loss-of-coolant-accidents-in-a-bwr6-nuclear-power-plant" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/92352.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">343</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">1</span> CFD Simulation for Flow Behavior in Boiling Water Reactor Vessel and Upper Pool under Decommissioning Condition</h5> <div class="card-body"> <p class="card-text"><strong>Authors:</strong> <a href="https://publications.waset.org/abstracts/search?q=Y.%20T.%20Ku">Y. T. Ku</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=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=Y.%20F.%20Chang"> Y. F. Chang</a> </p> <p class="card-text"><strong>Abstract:</strong></p> In order to respond the policy decision of non-nuclear homes, Tai Power Company (TPC) will provide the decommissioning project of Kuosheng Nuclear power plant (KSNPP) to meet the regulatory requirement in near future. In this study, the computational fluid dynamics (CFD) methodology has been employed to develop a flow prediction model for boiling water reactor (BWR) with upper pool under decommissioning stage. The model can be utilized to investigate the flow behavior as the vessel combined with upper pool and continuity cooling system. At normal operating condition, different parameters are obtained for the full fluid area, including velocity, mass flow, and mixing phenomenon in the reactor pressure vessel (RPV) and upper pool. Through the efforts of the study, an integrated simulation model will be developed for flow field analysis of decommissioning KSNPP under normal operating condition. It can be expected that a basis result for future analysis application of TPC can be provide from this study. <p class="card-text"><strong>Keywords:</strong> <a href="https://publications.waset.org/abstracts/search?q=CFD" title="CFD">CFD</a>, <a href="https://publications.waset.org/abstracts/search?q=BWR" title=" BWR"> BWR</a>, <a href="https://publications.waset.org/abstracts/search?q=decommissioning" title=" decommissioning"> decommissioning</a>, <a href="https://publications.waset.org/abstracts/search?q=upper%20pool" title=" upper pool"> upper pool</a> </p> <a href="https://publications.waset.org/abstracts/92505/cfd-simulation-for-flow-behavior-in-boiling-water-reactor-vessel-and-upper-pool-under-decommissioning-condition" class="btn btn-primary btn-sm">Procedia</a> <a href="https://publications.waset.org/abstracts/92505.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">267</span> </span> </div> </div> </div> </main> <footer> <div id="infolinks" class="pt-3 pb-2"> <div class="container"> <div style="background-color:#f5f5f5;" class="p-3"> <div class="row"> <div class="col-md-2"> <ul class="list-unstyled"> About <li><a href="https://waset.org/page/support">About Us</a></li> <li><a href="https://waset.org/page/support#legal-information">Legal</a></li> <li><a target="_blank" rel="nofollow" href="https://publications.waset.org/static/files/WASET-16th-foundational-anniversary.pdf">WASET celebrates its 16th foundational anniversary</a></li> </ul> </div> <div class="col-md-2"> <ul class="list-unstyled"> Account <li><a href="https://waset.org/profile">My Account</a></li> </ul> </div> <div class="col-md-2"> <ul class="list-unstyled"> Explore <li><a href="https://waset.org/disciplines">Disciplines</a></li> <li><a href="https://waset.org/conferences">Conferences</a></li> <li><a href="https://waset.org/conference-programs">Conference Program</a></li> <li><a href="https://waset.org/committees">Committees</a></li> <li><a href="https://publications.waset.org">Publications</a></li> </ul> </div> <div class="col-md-2"> <ul class="list-unstyled"> Research <li><a href="https://publications.waset.org/abstracts">Abstracts</a></li> <li><a href="https://publications.waset.org">Periodicals</a></li> <li><a href="https://publications.waset.org/archive">Archive</a></li> </ul> </div> <div class="col-md-2"> <ul class="list-unstyled"> Open Science <li><a target="_blank" rel="nofollow" href="https://publications.waset.org/static/files/Open-Science-Philosophy.pdf">Open Science Philosophy</a></li> <li><a target="_blank" rel="nofollow" href="https://publications.waset.org/static/files/Open-Science-Award.pdf">Open Science Award</a></li> <li><a target="_blank" rel="nofollow" href="https://publications.waset.org/static/files/Open-Society-Open-Science-and-Open-Innovation.pdf">Open Innovation</a></li> <li><a target="_blank" rel="nofollow" href="https://publications.waset.org/static/files/Postdoctoral-Fellowship-Award.pdf">Postdoctoral Fellowship Award</a></li> <li><a target="_blank" rel="nofollow" href="https://publications.waset.org/static/files/Scholarly-Research-Review.pdf">Scholarly Research Review</a></li> </ul> </div> <div class="col-md-2"> <ul class="list-unstyled"> Support <li><a href="https://waset.org/page/support">Support</a></li> <li><a href="https://waset.org/profile/messages/create">Contact Us</a></li> <li><a href="https://waset.org/profile/messages/create">Report Abuse</a></li> </ul> </div> </div> </div> </div> </div> <div class="container text-center"> <hr style="margin-top:0;margin-bottom:.3rem;"> <a href="https://creativecommons.org/licenses/by/4.0/" target="_blank" class="text-muted small">Creative Commons Attribution 4.0 International License</a> <div id="copy" class="mt-2">© 2024 World Academy of Science, Engineering and Technology</div> </div> </footer> <a href="javascript:" id="return-to-top"><i class="fas fa-arrow-up"></i></a> <div class="modal" id="modal-template"> <div class="modal-dialog"> <div class="modal-content"> <div class="row m-0 mt-1"> <div class="col-md-12"> <button type="button" class="close" data-dismiss="modal" aria-label="Close"><span aria-hidden="true">×</span></button> </div> </div> <div class="modal-body"></div> </div> </div> </div> <script src="https://cdn.waset.org/static/plugins/jquery-3.3.1.min.js"></script> <script src="https://cdn.waset.org/static/plugins/bootstrap-4.2.1/js/bootstrap.bundle.min.js"></script> <script src="https://cdn.waset.org/static/js/site.js?v=150220211556"></script> <script> jQuery(document).ready(function() { /*jQuery.get("https://publications.waset.org/xhr/user-menu", function (response) { jQuery('#mainNavMenu').append(response); });*/ jQuery.get({ url: "https://publications.waset.org/xhr/user-menu", cache: false }).then(function(response){ jQuery('#mainNavMenu').append(response); }); }); </script> </body> </html>