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1
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Batyrbekov E, Vityuk V, Vurim A, Vityuk G. Experimental opportunities and main results of the impulse graphite reactor use for research in safety area. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2022.109582] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 12/03/2022]
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2
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Zhang T, Morita K, Liu X, Liu W, Kamiyama K. A 3D particle-based simulation of heat and mass transfer behavior in the EAGLE ID1 in-pile test. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109389] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/01/2022]
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3
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Mukhamedov N, Tskhe V, Sapatayev Y, Kukushkin I. Microstructure and mechanical properties of the LWR solidified melt prototype obtained by the out-of-pile experiment. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108594] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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4
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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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5
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Affiliation(s)
- Colby Jensen
- Idaho National Laboratory, 2525 North Fremont Avenue, Idaho Falls, Idaho
| | - Austin Fleming
- Idaho National Laboratory, 2525 North Fremont Avenue, Idaho Falls, Idaho
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6
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Bachrata A, Trotignon L, Sciora P, Saez M. A three-dimensional neutronics – Thermalhydraulics Unprotected Loss of Flow simulation in Sodium-cooled Fast Reactor with mitigation devices. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.02.015] [Citation(s) in RCA: 5] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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7
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Vityuk V, Vurim A. Method for determining the energy parameters in pulse reactor experiments. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2018.12.013] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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8
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Usov EV, Lobanov PD, Klimonov IA, Kutlimetov AE, Butov AA, Chukhno VI, Kudashov IG, Svetonosov AI, Pribaturin NA. Numerical investigations of stainless steel melt motions on the surface of uranium dioxide. EPJ WEB OF CONFERENCES 2019. [DOI: 10.1051/epjconf/201919600005] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
The paper contains the results of numerical simulation of stainless steel melt motions on the surface of uranium dioxide. The investigations are performed for purposes of understanding of the fuel rod behavior during the core disruptive accident in the fast reactors. The systems of mass, energy and momentum conservation equations are solved to simulate melt motion on the surface of the fuel pin. Heat transfer and friction between melt and pin's surface and melt and coolant flow are taken into consideration. The dependences of mass of the melt and the features of the melt motion on coolant velocity and contact angle between melt and surface of the fuel rod are presented.
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9
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Chikazawa Y, Aoto K, Hayafune H, Kotake S, Ohno Y, Ito T, Toda M. Evaluation of JSFR Key Technologies. NUCL TECHNOL 2017. [DOI: 10.13182/nt179-360] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Yoshitaka Chikazawa
- Japan Atomic Energy Agency, 4002 Narita Oarai Higashi-ibaraki-gun Ibaraki 311-1393, Japan
| | - Kazumi Aoto
- Japan Atomic Energy Agency, 4002 Narita Oarai Higashi-ibaraki-gun Ibaraki 311-1393, Japan
| | - Hiroki Hayafune
- Japan Atomic Energy Agency, 4002 Narita Oarai Higashi-ibaraki-gun Ibaraki 311-1393, Japan
| | - Shoji Kotake
- Japan Atomic Power Company Ltd., 1-1, Mitoshiro-chyo, Kanda Chiyoda-ku, Tokyo 101-0053, Japan
| | - Yushi Ohno
- Japan Atomic Power Company Ltd., 1-1, Mitoshiro-chyo, Kanda Chiyoda-ku, Tokyo 101-0053, Japan
| | - Takaya Ito
- Mitsubishi FBR Systems Inc., 2-34-17, Jingumae, Shibuya-ku, Tokyo 105-001, Japan
| | - Mikio Toda
- Mitsubishi FBR Systems Inc., 2-34-17, Jingumae, Shibuya-ku, Tokyo 105-001, Japan
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The path for innovative severe accident neutronics studies in ZPRs. Part I.1 - Analysis of SNEAK-12A experiments for core disruption in LMFBRs. PROGRESS IN NUCLEAR ENERGY 2017. [DOI: 10.1016/j.pnucene.2016.11.001] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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11
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Vityuk VA, Vurim AD, Kotov VM, Pakhnits AV. Determination of the Parameters for Fuel Assembly Tests in a Pulsed Graphite Reactor. ATOM ENERGY+ 2016. [DOI: 10.1007/s10512-016-0138-3] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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12
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Ravi L, Velusamy K, Chellapandi P. Conjugate heat transfer investigation of core damage propagation during total instantaneous blockage in SFR fuel subassembly. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2015.09.032] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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13
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Suzuki T, Tobita Y, Nakai R. Evaluation of recriticality behavior in the material-relocation phase for Japan sodium-cooled fast reactor. J NUCL SCI TECHNOL 2015. [DOI: 10.1080/00223131.2015.1005719] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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14
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Suzuki T, Tobita Y, Kawada K, Tagami H, Sogabe J, Matsuba K, Ito K, Ohshima H. A preliminary evaluation of unprotected loss-of-flow accident for a prototype fast-breeder reactor. NUCLEAR ENGINEERING AND TECHNOLOGY 2015. [DOI: 10.1016/j.net.2015.03.001] [Citation(s) in RCA: 17] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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15
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Uematsu MM, Prèle G, Mariteau P, Sauvage JF, Hayafune H, Chikazawa Y. Comparison of JSFR design with EDF requirements for future SFR. J NUCL SCI TECHNOL 2015. [DOI: 10.1080/00223131.2014.953015] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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16
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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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17
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Suzuki T, Kamiyama K, Yamano H, Kubo S, Tobita Y, Nakai R, Koyama K. A scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retention. J NUCL SCI TECHNOL 2014. [DOI: 10.1080/00223131.2013.877405] [Citation(s) in RCA: 44] [Impact Index Per Article: 4.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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18
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Kamiyama K, Saito M, Matsuba KI, Isozaki M, Sato I, Konishi K, Zuyev VA, Kolodeshnikov AA, Vassiliev YS. Experimental study on fuel-discharge behaviour through in-core coolant channels. J NUCL SCI TECHNOL 2013. [DOI: 10.1080/00223131.2013.785272] [Citation(s) in RCA: 14] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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19
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Yamano H, Sato I, Tobita Y. Development of technical basis in the initiating and transition phases of unprotected events for Level-2 PSA methodology in sodium-cooled fast reactors. NUCLEAR ENGINEERING AND DESIGN 2012. [DOI: 10.1016/j.nucengdes.2011.08.049] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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20
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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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22
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Morita K, Zhang S, Koshizuka S, Tobita Y, Yamano H, Shirakawa N, Inoue F, Yugo H, Naitoh M, Okada H, Yamamoto Y, Himi M, Hirano E, Shimizu S, Oue M. Detailed analyses of key phenomena in core disruptive accidents of sodium-cooled fast reactors by the COMPASS code. NUCLEAR ENGINEERING AND DESIGN 2011. [DOI: 10.1016/j.nucengdes.2011.03.038] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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23
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Matsuo E, Abe Y, Chitose K, Koyama K, Itoh K. Study on jet breakup behavior at core disruptive accident for fast breeder reactor. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.11.011] [Citation(s) in RCA: 50] [Impact Index Per Article: 3.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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