Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code
Many reactor safety simulation codes for nuclear power plants (NPPs) have been developed. However, it is very important to evaluate these codes by testing different accident scenarios in actual plant conditions. In reactor analysis, small break loss of coolant accident (SBLOCA) is an important safet...
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| Format: | Article |
| Language: | English |
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Wiley
2017-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2017/4762709 |
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| author | Eltayeb Yousif Zhijian Zhang Zhaofei Tian Hao-ran Ju |
| author_facet | Eltayeb Yousif Zhijian Zhang Zhaofei Tian Hao-ran Ju |
| author_sort | Eltayeb Yousif |
| collection | DOAJ |
| description | Many reactor safety simulation codes for nuclear power plants (NPPs) have been developed. However, it is very important to evaluate these codes by testing different accident scenarios in actual plant conditions. In reactor analysis, small break loss of coolant accident (SBLOCA) is an important safety issue. RELAP5-MV Visualized Modularization software is recognized as one of the best estimate transient simulation programs of light water reactors (LWR). RELAP5-MV has new options for improved modeling methods and interactive graphics display. Though the same models incorporated in RELAP5/MOD 4.0 are in RELAP5-MV, the significant difference of the latter is the interface for preparing the input deck. In this paper, RELAP5-MV is applied for the transient analysis of the primary system variation of thermal hydraulics parameters in primary loop under SBLOCA in AP1000 NPP. The upper limit of SBLOCA (10 inches) is simulated in the cold leg of the reactor and the calculations performed up to a transient time of 450,000.0 s. The results obtained from RELAP5-MV are in good agreement with those of NOTRUMP code obtained by Westinghouse when compared under the same conditions. It can be easily inferred that RELAP5-MV, in a similar manner to RELAP5/MOD4.0, is suitable for simulating a SBLOCA scenario. |
| format | Article |
| id | doaj-art-069e331d5e8e4ef0815e66dc6b53fba4 |
| institution | Kabale University |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2017-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-069e331d5e8e4ef0815e66dc6b53fba42025-02-03T01:09:32ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832017-01-01201710.1155/2017/47627094762709Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP CodeEltayeb Yousif0Zhijian Zhang1Zhaofei Tian2Hao-ran Ju3College of Nuclear Science and Technology, Harbin Engineering University, 145 Nantong Street, Harbin, Heilongjiang 150001, ChinaCollege of Nuclear Science and Technology, Harbin Engineering University, 145 Nantong Street, Harbin, Heilongjiang 150001, ChinaCollege of Nuclear Science and Technology, Harbin Engineering University, 145 Nantong Street, Harbin, Heilongjiang 150001, ChinaCollege of Nuclear Science and Technology, Harbin Engineering University, 145 Nantong Street, Harbin, Heilongjiang 150001, ChinaMany reactor safety simulation codes for nuclear power plants (NPPs) have been developed. However, it is very important to evaluate these codes by testing different accident scenarios in actual plant conditions. In reactor analysis, small break loss of coolant accident (SBLOCA) is an important safety issue. RELAP5-MV Visualized Modularization software is recognized as one of the best estimate transient simulation programs of light water reactors (LWR). RELAP5-MV has new options for improved modeling methods and interactive graphics display. Though the same models incorporated in RELAP5/MOD 4.0 are in RELAP5-MV, the significant difference of the latter is the interface for preparing the input deck. In this paper, RELAP5-MV is applied for the transient analysis of the primary system variation of thermal hydraulics parameters in primary loop under SBLOCA in AP1000 NPP. The upper limit of SBLOCA (10 inches) is simulated in the cold leg of the reactor and the calculations performed up to a transient time of 450,000.0 s. The results obtained from RELAP5-MV are in good agreement with those of NOTRUMP code obtained by Westinghouse when compared under the same conditions. It can be easily inferred that RELAP5-MV, in a similar manner to RELAP5/MOD4.0, is suitable for simulating a SBLOCA scenario.http://dx.doi.org/10.1155/2017/4762709 |
| spellingShingle | Eltayeb Yousif Zhijian Zhang Zhaofei Tian Hao-ran Ju Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code Science and Technology of Nuclear Installations |
| title | Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code |
| title_full | Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code |
| title_fullStr | Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code |
| title_full_unstemmed | Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code |
| title_short | Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code |
| title_sort | simulation and analysis of small break loca for ap1000 using relap5 mv and its comparison with notrump code |
| url | http://dx.doi.org/10.1155/2017/4762709 |
| work_keys_str_mv | AT eltayebyousif simulationandanalysisofsmallbreaklocaforap1000usingrelap5mvanditscomparisonwithnotrumpcode AT zhijianzhang simulationandanalysisofsmallbreaklocaforap1000usingrelap5mvanditscomparisonwithnotrumpcode AT zhaofeitian simulationandanalysisofsmallbreaklocaforap1000usingrelap5mvanditscomparisonwithnotrumpcode AT haoranju simulationandanalysisofsmallbreaklocaforap1000usingrelap5mvanditscomparisonwithnotrumpcode |