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Kumar Panigrahi P, Velusamy K, Natesan K, Devan K. Numerical investigation of thermal failure of a fuel subassembly foot wall during molten material relocation under various flow blockage scenarios in sodium-cooled fast reactor. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.112047] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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Panigrahi PK, Velusamy K. Thermal-hydraulic analysis of FAIDUS design for severe accident mitigation strategy in a medium size sodium-cooled fast reactor. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111222] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Zhang T, Funakoshi K, Liu X, Liu W, Morita K, Kamiyama K. Numerical simulation of heat transfer behavior in EAGLE ID1 in-pile test using finite volume particle method. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.107856] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Chitose K, Takaki N. Convex shaped FBR core with graded size pins to prevent re-criticality during Core Disruptive Accident. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2018.12.022] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Gabrielli F, Maschek W, Li R, Boccaccini CM, Flad M, Gianfelici S, Vezzoni B, Rineiski A. Probabilistic evaluation of the energetics upper bound during the transition phase of an unprotected loss of flow accident for a sodium cooled fast reactor by using a Phenomenological Relationship Diagram. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2018.11.004] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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Maschek W, Li R, Matzerath Boccaccini C, Gabrielli F, Morita K. Investigation on upper bounds of recriticality energetics of hypothetical core disruptive accidents in sodium cooled fast reactors. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2017.11.002] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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Tobita Y, Kamiyama K, Tagami H, Matsuba KI, Suzuki T, Isozaki M, Yamano H, Morita K, Guo L, Zhang B. Development of the evaluation methodology for the material relocation behavior in the core disruptive accident of sodium-cooled fast reactors. J NUCL SCI TECHNOL 2016. [DOI: 10.1080/00223131.2016.1143409] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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Kamiyama K, Konishi K, Sato I, Toyooka JI, Matsuba KI, Zuyev VA, Pakhnits AV, Vityuk VA, Vurim AD, Gaidaichuk VA, Kolodeshnikov AA, Vassiliev YS. Experimental studies on the upward fuel discharge for elimination of severe recriticality during core-disruptive accidents in sodium-cooled fast reactors. J NUCL SCI TECHNOL 2014. [DOI: 10.1080/00223131.2014.912566] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Kotake S, Yamano H, Sagayama Y. Safety Design Approach for a Large-Scale Japan Sodium-Cooled Fast Reactor (JSFR). FUSION SCIENCE AND TECHNOLOGY 2012. [DOI: 10.13182/fst12-a13410] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Shoji Kotake
- Japan Atomic Energy Agency; 2-2-2 Uchisaiwai, Chiyoda, Tokyo, 100-0011 Japan;
| | - Hidemasa Yamano
- Japan Atomic Energy Agency; 2-2-2 Uchisaiwai, Chiyoda, Tokyo, 100-0011 Japan;
| | - Yutaka Sagayama
- Japan Atomic Energy Agency; 2-2-2 Uchisaiwai, Chiyoda, Tokyo, 100-0011 Japan;
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Safety Design and Evaluation in a Large-Scale Japan Sodium-Cooled Fast Reactor. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2012. [DOI: 10.1155/2012/614973] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
Abstract
As a next-generation plant, a large-scale Japan sodium-cooled fast reactor (JSFR) adopts a number of innovative technologies in order to achieve economic competitiveness, enhanced reliability, and safety. This paper describes safety requirements for JSFR conformed to the defense-in-depth principle in IAEA. Specific design features of JSFR are a passive reactor shutdown system and a recriticality-free concept against anticipated transients without scram (ATWS) in design extension conditions (DECs). A fully passive decay heat removal system with natural circulation is also introduced for design-basis events (DBEs) and DECs. In this paper, the safety design accommodation in JSFR was validated by safety analyses for representative DBEs: primary pump seizure and long-term loss-of-offsite power accidents. The safety analysis also showed the effectiveness of the passive shutdown system against a typical ATWS. Severe accident analysis supported by safety experiments and phenomenological consideration led to the feasibility of in-vessel retention without energetic recriticality. Moreover, a probabilistic safety assessment indicated to satisfy the risk target.
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Prevention and mitigation of severe accident developments and recriticalities in advanced fast reactor systems. PROGRESS IN NUCLEAR ENERGY 2011. [DOI: 10.1016/j.pnucene.2011.04.008] [Citation(s) in RCA: 10] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Ishizu T, ENDO H, NINOKATA H. On Void Reactivity Limitation for the Core Loaded with Mixed Nitride Fuels. J NUCL SCI TECHNOL 2009. [DOI: 10.1080/18811248.2009.9711607] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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Konishi K, Toyooka JI, Kamiyama K, Sato I, Kubo S, Kotake S, Koyama K, Vurim AD, Gaidaichuk VA, Pakhnits AV, Vassiliev YS. The result of a wall failure in-pile experiment under the EAGLE project. NUCLEAR ENGINEERING AND DESIGN 2007. [DOI: 10.1016/j.nucengdes.2007.03.012] [Citation(s) in RCA: 33] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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