(A) new two-step method with improved nodal equivalence for PWR analysis and design가압경수로 해석 및 설계를 위한 노달 등가성이 개선된 2단계 방법

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Despite a lot of progress in high-fidelity transport-based analysis of nuclear reactors, the conventional two-step method is expected to continue to play a key role in commercial pressurized water reactor (PWR) design due to its merits of having acceptable accuracy and cost. However, it is well known that the popularly-used neighbor- and spectrum-irrelevant leakage correction in the conventional method causes some errors in prediction of the core reactivity and power distribution. First, the intrinsic limitations of the conventional two-step methods are discussed by analyzing a two-dimensional small modular reactor (SMR) core with the DeCART2D/MASTER code system. This thesis suggests a new two-step method that could improve solution accuracy by overcoming the inherent drawbacks of the conventional 2-step method. The new method adopts the albedo-corrected parameterized equivalence constants (APEC) method to correct the lattice-based raw cross-sections (XSs) and discontinuity factors (DFs) by accounting for the actual neutron leakage. For a full-scope development and implementation of the APEC correction, the MASTER nodal code was modified so that the group constants can be corrected in the middle of a microscopic core depletion. The color-set models are defined to determine the APEC functions for burnup-dependent XS and DF corrections. Then the new two-step method was applied to depletion analyses of the SMR without thermal feedback, and its validity was evaluated in view of the prediction capability of the reactor eigenvalue and nodal power profile. In addition, four variants of the original SMR core and a large PWR core were analyzed for a further evaluation of the APEC-assisted depletion. In this study, several combinations of the burnup-dependent and -independent XS and DF corrections were also considered. The numerical results show that this advanced method could enhance the nodal equivalence significantly with inexpensive additional costs. Therefore, it is expected that affordable sufficient-fidelity diffusion-based analysis may be possible for PWRs.
Advisors
Kim, Yongheeresearcher김용희researcher
Description
한국과학기술원 :원자력및양자공학과,
Publisher
한국과학기술원
Issue Date
2019
Identifier
325007
Language
eng
Description

학위논문(박사) - 한국과학기술원 : 원자력및양자공학과, 2019.8,[v, 92 p. :]

Keywords

two-step method▼aleakage correction▼aAPEC method▼across-section▼adiscontinuity factor▼anodal equivalence▼asufficient-fidelity diffusion-based analysis; 2단계 방법▼a누설 보정▼a알베도 기반 등가상수 보정 방법▼a단면적▼a불연속 인자▼a노달 등가성▼a충분한 정밀도의 확산 해석

URI
http://hdl.handle.net/10203/283255
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=871424&flag=dissertation
Appears in Collection
NE-Theses_Ph.D.(박사논문)
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