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Generalization of the tibere B1 leakage model to the method of characteristics. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109160] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Verification of SARAX code system in the reactor core transient calculation based on the simplified EBR-II benchmark. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2021.10.045] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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Magni A, Pizzocri D, Luzzi L, Lainet M, Michel B. Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.02.003] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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Wei L, Zheng Y, Du X, Liu S, Kang C, Liu Z, Wang Y, Xiao B. Development of SARAX code system for full-range spectrum adaptability in advanced reactor analysis. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108664] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/01/2022]
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Wei L, Zheng Y, Du X, Wu H. Extension of SARAX code system for reactors with intermediate spectrum. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110883] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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6
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Du X, Zheng Y, Wang Y, Zhai Z, Zhou H. Validation of SARAX code system using the SFR operational tests. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107744] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Sciora P, Buiron L, Varaine F. The low void worth core design (‘CFV’) based on an axially heterogeneous geometry. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110763] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Wei L, Zheng Y, Wu H. Improvement of few-group cross-section generation in fast reactor analysis system SARAX. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.04.026] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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Guo H, Garcia E, Faure B, Buiron L, Archier P, Sciora P, Rimpault G. Advanced method for neutronic simulation of control rods in sodium fast reactors: Numerical and experimental validation. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.01.042] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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Faure B, Archier P, Vidal JF, Buiron L. A 2D/1D Algorithm for Effective Cross-Section Generation in Fast Reactor Neutronic Transport Calculations. NUCL SCI ENG 2018. [DOI: 10.1080/00295639.2018.1480190] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
Affiliation(s)
- Bastien Faure
- CEA, DEN, DER, SPRC, Cadarache, Saint-Paul-lez-Durance F-13108, France
| | - Pascal Archier
- CEA, DEN, DER, SPRC, Cadarache, Saint-Paul-lez-Durance F-13108, France
| | | | - Laurent Buiron
- CEA, DEN, DER, SPRC, Cadarache, Saint-Paul-lez-Durance F-13108, France
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