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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.2
- 수록면
- 399 - 413 (15page)
- DOI
- https://doi.org/10.1016/j.net.2020.07.004
이용수
초록· 키워드
오류제보하기
The solution of the time-dependent neutron diffusion equation can be approximated using quasi-staticmethods that factorise the neutronic flux as the product of a time dependent function times a shapefunction that depends both on space and time. A generalization of this technique is the updated modalmethod. This strategy assumes that the neutron flux can be decomposed into a sum of amplitudesmultiplied by some shape functions. These functions, known as modes, come from the solution of theeigenvalue problems associated with the static neutron diffusion equation that are being updated alongthe transient. In previous works, the time step used to update the modes is set to a fixed value and thisimplies the need of using small time-steps to obtain accurate results and, consequently, a highcomputational cost. In this work, we propose the use of an adaptive control time-step that reducesautomatically the time-step when the algorithm detects large errors and increases this value when it isnot necessary to use small steps. Several strategies to compute the modes updating time step are proposedand their performance is tested for different transients in benchmark reactors with rectangularand hexagonal geometry
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참고문헌 (38)
참고문헌 신청
A. Vidal-Ferrandiz / 2014 / Solution of the lambda modes problem of a nuclear power reactor using an h-p finite element method / Ann. Nucl. Energy 72:338~349
W. Stacey / 1969 / Space-time Nuclear Reactor Kinetics, vol. 5 / Academic Press
K. Ott / 1969 / Accuracy of the quasistatic treatment of spatial reactor kinetics / Nucl. Sci. Eng 36(3):402~411
S. Dulla / 2004 / Neutron kinetics of fluidefuel systems by the quasi-static method / Ann. Nucl. Energy 31(15):1709~1733
S. Dulla / 2008 / The quasi-static method revisited / Prog. Nucl. Energy 50(8):908~920
W. Stacey / 1969 / Space-time Nuclear Reactor Kinetics, vol. 5 / Academic Press
K. Ott / 1969 / Accuracy of the quasistatic treatment of spatial reactor kinetics / Nucl. Sci. Eng 36(3):402~411
S. Dulla / 2004 / Neutron kinetics of fluidefuel systems by the quasi-static method / Ann. Nucl. Energy 31(15):1709~1733
S. Dulla / 2008 / The quasi-static method revisited / Prog. Nucl. Energy 50(8):908~920
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