Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE
Online ISSN : 2424-2934
2019.27
セッションID: 1681
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DEVELOPMENT AND VERIFICATION OF POINT-DEPLETION CODE FOR PWR
*Yunfei ZhangQian ZhangQiang ZhaoXiaomiao ChiZhijian ZhangKai Huang
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会議録・要旨集 認証あり

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In the field of the reactor computational physics, the burnup equation is established according to the burnup chain, and the solution of burnup equation is the core of the burnup calculation. A point-depletion code for PWR is developed based on Chebyshev Rational Approximation Method (CRAM). There are two burnup libraries applied in this code: the 1487-isotopes library used for the coupling with Monte Carlo code and the simplified library used for the coupling with deterministic transport code. A series of benchmark problems are performed for the verification of the point-depletion code. Numerical results show that this code can obtain high accuracy in the burnup calculation compared with the reference results.
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© 2019 The Japan Society of Mechanical Engineers
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