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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.12
- 수록면
- 3,930 - 3,943 (14page)
- DOI
- https://doi.org/10.1016/j.net.2021.06.018
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초록· 키워드
오류제보하기
To improve the capability of the SAS4A code, which simulates the initiating phase of core disruptiveaccidents for MOX-fueled Sodium-cooled Fast Reactors (SFRs), the authors have investigated in detail thephysical phenomena under unprotected loss-of-flow (ULOF) conditions in a previous paper (Kawada andSuzuki, 2020) [1]. As the conclusion of the last article, fuel stub motion, in which the residual fuel pelletswould move toward the core central region after fuel pin disruption, was identified as one of the keyphenomena to be appropriately simulated for the initiating phase of ULOF.
In the present paper, based on the analysis of the experimental data, the behaviors related to the stubmotion were evaluated and quantified by the author from scratch. A simple model describing fuel stubmotion, which was not modeled in the previous SAS4A code, was newly proposed. The applicability ofthe proposed model was validated through a series of analyses for the CABRI experiments, by which thestub motion would be represented with reasonable conservativeness for the reactivity evaluation ofdisrupted core
목차
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참고문헌 (16)
참고문헌 신청
K. Kawada / 2020 / Study on dominant aspects of unprotected loss-of-flow to be evaluated in the initiating phase for a sodium-cooled fast reactor / J. Nucl. Sci. Technol :1~14
A.M. Tentner / 1988 / Simulating unprotected accidents for advanced liquid metal reactors using the SAS4A accident analysis code / Conference of the Society of Computer Simulation
K. Kawada / 2014 / Development of PIRT (phenomena identification and ranking table) for SAS-SFR (SAS4A)validation, July 7-11 / 22nd International Conference on Nuclear Engineering
K. Kawada / 2014 / Preliminary result of validation study in SAS-SFR(SAS4A) code in simulated top and undercooled overpower conditions / 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10)
K. Kawada / 2016 / Validation study in SAS4A code in simulated mild TOP condition / Transactions of the American Nuclear Society 115:1597~1598
A.M. Tentner / 1988 / Simulating unprotected accidents for advanced liquid metal reactors using the SAS4A accident analysis code / Conference of the Society of Computer Simulation
K. Kawada / 2014 / Development of PIRT (phenomena identification and ranking table) for SAS-SFR (SAS4A)validation, July 7-11 / 22nd International Conference on Nuclear Engineering
K. Kawada / 2014 / Preliminary result of validation study in SAS-SFR(SAS4A) code in simulated top and undercooled overpower conditions / 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety (NUTHOS-10)
K. Kawada / 2016 / Validation study in SAS4A code in simulated mild TOP condition / Transactions of the American Nuclear Society 115:1597~1598
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