Валідація теплогідравлічної моделі реактора ВВЕР-1000/В-320 для розрахункового кода TRACE
The basic features of the development process, results of validation and their analysis are presented in the paper. VVER 1000/V-320 thermohydraulic model for TRACE computer code was developed. Validation calculation with this model was performed to confirm that this model is capable of simulating VV...
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| Дата: | 2017 |
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| Автори: | , , , |
| Формат: | Стаття |
| Мова: | English |
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State Scientific and Technical Center for Nuclear and Radiation Safety
2017
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| Онлайн доступ: | https://nuclear-journal.com/index.php/journal/article/view/130 |
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| Назва журналу: | Nuclear and Radiation Safety |
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oai:ojs2.nuclear-journal.com:article-1302019-03-02T07:38:26Z Development and Validation of VVER-1000 Thermohydraulic Computer Model for TRACE Computer Code Валідація теплогідравлічної моделі реактора ВВЕР-1000/В-320 для розрахункового кода TRACE Yanovskii, S. Zhabin, O. Vorobyov, Yu. Vyshemirskii, M. The basic features of the development process, results of validation and their analysis are presented in the paper. VVER 1000/V-320 thermohydraulic model for TRACE computer code was developed. Validation calculation with this model was performed to confirm that this model is capable of simulating VVER 1000/V-320 nuclear power plant response during transients and accidents. At the initial step of TRACE thermohydraulic model validation for VVER 1000/V-320, the initial and boundary conditions corresponding to the transient being evaluated were incorporated into the model and preliminary calculation was performed. The calculation results were compared with plant instrumentation data. The following representative transients for which detailed plant instrumentation records are available were selected for validation calculation is “Rivne NPP (RNPP) Unit 3 pressurizer pilot operated relief valve (PORV) stuck in open position during scheduled tests”. An experience that has been obtained, expanded opportunities of the SSTC NRS to use modern codes in the scientific and technical support of NRC. Описано основні особливості розробки і підходи для валідації моделі реактора ВВЕР-1000 /В-320. За результатами валідації підтверджено застосовність розробленої моделі для виконання детерміністичного аналізу безпеки. State Scientific and Technical Center for Nuclear and Radiation Safety 2017-02-27 Article Article application/pdf https://nuclear-journal.com/index.php/journal/article/view/130 10.32918/nrs.2017.1(73).07 Nuclear and Radiation Safety; No 1(73) (2017): Nuclear and Radiation Safety Ядерна та радіаційна безпека; № 1(73) (2017): Ядерна та радіаційна безпека 2073-6231 en https://nuclear-journal.com/index.php/journal/article/view/130/126 |
| institution |
Nuclear and Radiation Safety |
| collection |
OJS |
| language |
English |
| format |
Article |
| author |
Yanovskii, S. Zhabin, O. Vorobyov, Yu. Vyshemirskii, M. |
| spellingShingle |
Yanovskii, S. Zhabin, O. Vorobyov, Yu. Vyshemirskii, M. Валідація теплогідравлічної моделі реактора ВВЕР-1000/В-320 для розрахункового кода TRACE |
| author_facet |
Yanovskii, S. Zhabin, O. Vorobyov, Yu. Vyshemirskii, M. |
| author_sort |
Yanovskii, S. |
| title |
Валідація теплогідравлічної моделі реактора ВВЕР-1000/В-320 для розрахункового кода TRACE |
| title_short |
Валідація теплогідравлічної моделі реактора ВВЕР-1000/В-320 для розрахункового кода TRACE |
| title_full |
Валідація теплогідравлічної моделі реактора ВВЕР-1000/В-320 для розрахункового кода TRACE |
| title_fullStr |
Валідація теплогідравлічної моделі реактора ВВЕР-1000/В-320 для розрахункового кода TRACE |
| title_full_unstemmed |
Валідація теплогідравлічної моделі реактора ВВЕР-1000/В-320 для розрахункового кода TRACE |
| title_sort |
валідація теплогідравлічної моделі реактора ввер-1000/в-320 для розрахункового кода trace |
| title_alt |
Development and Validation of VVER-1000 Thermohydraulic Computer Model for TRACE Computer Code |
| description |
The basic features of the development process, results of validation and their analysis are presented in the paper. VVER 1000/V-320 thermohydraulic model for TRACE computer code was developed. Validation calculation with this model was performed to confirm that this model is capable of simulating VVER 1000/V-320 nuclear power plant response during transients and accidents.
At the initial step of TRACE thermohydraulic model validation for VVER 1000/V-320, the initial and boundary conditions corresponding to the transient being evaluated were incorporated into the model and preliminary calculation was performed. The calculation results were compared with plant instrumentation data.
The following representative transients for which detailed plant instrumentation records are available were selected for validation calculation is “Rivne NPP (RNPP) Unit 3 pressurizer pilot operated relief valve (PORV) stuck in open position during scheduled tests”. An experience that has been obtained, expanded opportunities of the SSTC NRS to use modern codes in the scientific and technical support of NRC. |
| publisher |
State Scientific and Technical Center for Nuclear and Radiation Safety |
| publishDate |
2017 |
| url |
https://nuclear-journal.com/index.php/journal/article/view/130 |
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2024-09-01T17:39:07Z |
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2024-09-01T17:39:07Z |
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