(A) hybrid accident simulation methodology for nuclear power plant by combining thermal-hydraulic program and artificial neural networks열수력프로그램과 인공신경회로망을 합성한 원전 사고모의방법

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Compact simulators for nuclear power plants can be used as cost-effective training or analysis tools; generally, they demonstrate overall responses of transients or accidents in real time or faster. In the thermal-hydraulic models of compact simulators, governing equations are simplified with reasonable assumptions and empirical correlations, and approximate solutions are obtained by using appropriate numerical schemes. Moreover, many physical control volumes in plant modeling are lumped to reduce the computing time. The simplification of equations and reduction of control volume numbers usually degrade the accuracy of solutions. A hybrid accident simulation methodology is proposed to enhance the capabilities of a compact simulator by introducing artificial neural networks. A simplified thermal-hydraulic program, playing the role of compact simulator, is designed to calculate the overall responses of transients and accidents. Two neural networks are designed and trained with the target values obtained from the analyses of detailed computer codes and trained results are combined with the simplified thermal-hydraulic program to perform the following roles: (i) compensation for inaccuracy of a simplified thermal-hydraulic program occurring from simplified governing equation and small number of physical control volumes: the auto-associative neural network (AANN), trained with the target values obtained from RELAP5/MOD3 code analyses, improves the calculated results of the simplified thermal-hydraulic program, and (ii) prediction of the critical parameter usually calculated from the sophisticated computer code: the back propagation neural network (BPN), trained with the target values obtained from COBRA-IV code analyses, predicts the minimum departure from nucleate boiling ratio (DNBR) which is not calculated in simplified thermal-hydraulic program. Simulations for the several accidents are carried out to verify the applicability of the proposed methodology. The ver...
Advisors
Chang, Soon-Heungresearcher장순흥researcher
Description
한국과학기술원 : 원자력및양자공학과,
Publisher
한국과학기술원
Issue Date
2004
Identifier
237568/325007  / 000935374
Language
eng
Description

학위논문(박사) - 한국과학기술원 : 원자력및양자공학과, 2004.2, [ ix, 130 p. ]

Keywords

MINIMUM DEPARTURE FROM NUCLEATE BOILING RATIO; ACCIDENT ANALYSIS; NUCLEAR POWER PLANT; NEURAL NETWORK; THERMAL-HYDRAULIC PROGRAM; 열수력 프로그램; 최소 핵비등이탈률; 사고해석; 원자력발전소; 인공신경회로망

URI
http://hdl.handle.net/10203/48958
Link
http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=237568&flag=dissertation
Appears in Collection
NE-Theses_Ph.D.(박사논문)
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