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Title: Nuclear reactor transient analysis via a quasi-static kinetics Monte Carlo method

The predictor-corrector quasi-static (PCQS) method is applied to the Monte Carlo (MC) calculation for reactor transient analysis. To solve the transient fixed-source problem of the PCQS method, fission source iteration is used and a linear approximation of fission source distributions during a macro-time step is introduced to provide delayed neutron source. The conventional particle-tracking procedure is modified to solve the transient fixed-source problem via MC calculation. The PCQS method with MC calculation is compared with the direct time-dependent method of characteristics (MOC) on a TWIGL two-group problem for verification of the computer code. Then, the results on a continuous-energy problem are presented.
Authors:
; ;  [1]
  1. Korea Advanced Institute of Science and Technology 291 Daehak-ro, Yuseong-gu, Daejeon, Korea 305-701 (Korea, Republic of)
Publication Date:
OSTI Identifier:
22499108
Resource Type:
Journal Article
Resource Relation:
Journal Name: AIP Conference Proceedings; Journal Volume: 1702; Journal Issue: 1; Conference: ICCMSE 2015: International conference of computational methods in sciences and engineering 2015, Athens (Greece), 20-23 Mar 2015; Other Information: (c) 2015 AIP Publishing LLC; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; APPROXIMATIONS; COMPARATIVE EVALUATIONS; COMPUTER CODES; DELAYED NEUTRONS; FISSION; MONTE CARLO METHOD; REACTOR KINETICS; TIME DEPENDENCE; TRANSIENTS