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Title: Substantiation of parameters of the geometric model of the research reactor core for the calculation using the Monte Carlo method

The choice of the spatial nodalization for the calculation of the power density and burnup distribution in a research reactor core with fuel assemblies of the IRT-3M and VVR-KN type using the program based on the Monte Carlo code is described. The influence of the spatial nodalization on the results of calculating basic neutronic characteristics and calculation time is investigated.
Authors:
;  [1]
  1. National Research Nuclear University MEPhI (Russian Federation)
Publication Date:
OSTI Identifier:
22471960
Resource Type:
Journal Article
Resource Relation:
Journal Name: Physics of Atomic Nuclei; Journal Volume: 78; Journal Issue: 11; Other Information: Copyright (c) 2015 Pleiades Publishing, Ltd.; Country of input: International Atomic Energy Agency (IAEA)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BURNUP; COMPUTER CODES; FUEL ASSEMBLIES; MONTE CARLO METHOD; POWER DENSITY; REACTOR CORES; RESEARCH REACTORS; WWR TYPE REACTORS