Analysis of numerical studies on the thermal-hydraulic and neutronic thermal-hydraulic stability of supercritical water reactors
The paper presents a review of modern studies on the potential types of coolant flow instabilities in the supercritical water reactor core. These instabilities have a negative impact on the operational safety of nuclear power plants. Despite the impressive number of computational works devoted to th...
| Main Authors: | , , |
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| Format: | Article |
| Language: | English |
| Published: |
National Research Nuclear University (MEPhI)
2021-12-01
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| Series: | Nuclear Energy and Technology |
| Online Access: | https://nucet.pensoft.net/article/78368/download/pdf/ |
| _version_ | 1819009311827820544 |
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| author | Artavazd M. Sujyan Viktor I. Deev Vladimir S. Kharitonov |
| author_facet | Artavazd M. Sujyan Viktor I. Deev Vladimir S. Kharitonov |
| author_sort | Artavazd M. Sujyan |
| collection | DOAJ |
| description | The paper presents a review of modern studies on the potential types of coolant flow instabilities in the supercritical water reactor core. These instabilities have a negative impact on the operational safety of nuclear power plants. Despite the impressive number of computational works devoted to this topic, there still remain unresolved problems. The main disadvantages of the models are associated with the use of one simulated channel instead of a system of two or more parallel channels, the lack consideration for neutronic feedbacks, and the problem of choosing the design ratios for the heat transfer coefficient and hydraulic resistance coefficient under conditions of supercritical water flow. For this reason, it was decided to conduct an analysis that will make it possible to highlight the indicated problems and, on their basis, to formulate general requirements for a model of a nuclear reactor with a light-water supercritical pressure coolant. Consideration is also given to the features of the coolant flow stability in the supercritical water reactor core. In conclusion, the authors note the importance of further computational work using complex models of neutronic thermal-hydraulic stability built on the basis of modern achievements in the field of neutron physics and thermal physics. |
| first_indexed | 2024-12-21T00:54:21Z |
| format | Article |
| id | doaj.art-1232ee3371604777aa1cea21ace8810a |
| institution | Directory Open Access Journal |
| issn | 2452-3038 |
| language | English |
| last_indexed | 2024-12-21T00:54:21Z |
| publishDate | 2021-12-01 |
| publisher | National Research Nuclear University (MEPhI) |
| record_format | Article |
| series | Nuclear Energy and Technology |
| spelling | doaj.art-1232ee3371604777aa1cea21ace8810a2022-12-21T19:21:20ZengNational Research Nuclear University (MEPhI)Nuclear Energy and Technology2452-30382021-12-017431131810.3897/nucet.7.7836878368Analysis of numerical studies on the thermal-hydraulic and neutronic thermal-hydraulic stability of supercritical water reactorsArtavazd M. Sujyan0Viktor I. Deev1Vladimir S. Kharitonov2National Research Nuclear University MEPhINational Research Nuclear University MEPhINational Research Nuclear University MEPhIThe paper presents a review of modern studies on the potential types of coolant flow instabilities in the supercritical water reactor core. These instabilities have a negative impact on the operational safety of nuclear power plants. Despite the impressive number of computational works devoted to this topic, there still remain unresolved problems. The main disadvantages of the models are associated with the use of one simulated channel instead of a system of two or more parallel channels, the lack consideration for neutronic feedbacks, and the problem of choosing the design ratios for the heat transfer coefficient and hydraulic resistance coefficient under conditions of supercritical water flow. For this reason, it was decided to conduct an analysis that will make it possible to highlight the indicated problems and, on their basis, to formulate general requirements for a model of a nuclear reactor with a light-water supercritical pressure coolant. Consideration is also given to the features of the coolant flow stability in the supercritical water reactor core. In conclusion, the authors note the importance of further computational work using complex models of neutronic thermal-hydraulic stability built on the basis of modern achievements in the field of neutron physics and thermal physics.https://nucet.pensoft.net/article/78368/download/pdf/ |
| spellingShingle | Artavazd M. Sujyan Viktor I. Deev Vladimir S. Kharitonov Analysis of numerical studies on the thermal-hydraulic and neutronic thermal-hydraulic stability of supercritical water reactors Nuclear Energy and Technology |
| title | Analysis of numerical studies on the thermal-hydraulic and neutronic thermal-hydraulic stability of supercritical water reactors |
| title_full | Analysis of numerical studies on the thermal-hydraulic and neutronic thermal-hydraulic stability of supercritical water reactors |
| title_fullStr | Analysis of numerical studies on the thermal-hydraulic and neutronic thermal-hydraulic stability of supercritical water reactors |
| title_full_unstemmed | Analysis of numerical studies on the thermal-hydraulic and neutronic thermal-hydraulic stability of supercritical water reactors |
| title_short | Analysis of numerical studies on the thermal-hydraulic and neutronic thermal-hydraulic stability of supercritical water reactors |
| title_sort | analysis of numerical studies on the thermal hydraulic and neutronic thermal hydraulic stability of supercritical water reactors |
| url | https://nucet.pensoft.net/article/78368/download/pdf/ |
| work_keys_str_mv | AT artavazdmsujyan analysisofnumericalstudiesonthethermalhydraulicandneutronicthermalhydraulicstabilityofsupercriticalwaterreactors AT viktorideev analysisofnumericalstudiesonthethermalhydraulicandneutronicthermalhydraulicstabilityofsupercriticalwaterreactors AT vladimirskharitonov analysisofnumericalstudiesonthethermalhydraulicandneutronicthermalhydraulicstabilityofsupercriticalwaterreactors |