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Title: The Monte Carlo estimation of an effect of uncertainties in initial data on solving the transport equation by means of the MCU code

A new version of the tally module of the MCU software package is developed in which the approach for taking directly into account the uncertainty in initial data is implemented that is recommended by the international standard on estimating the uncertainty in results of measuring (ISO 13005). The new module makes it possible to evaluate the effect of uncertainty in initial data (caused by technological tolerances in fabrication of structural members of the core) on neutronic characteristics of the reactor. The developed software is adapted to parallel computing with the use of multiprocessor computers, which significantly reduces the computation time: the parallelization coefficient is almost equal to 1. Testing is performed by examples of solving the problem on criticality for the Godiva benchmark experiment and also for the infinite lattice of fuel assemblies of the VVER-440, VVER-1000, and VVER-1200. The results of calculations of the uncertainty in neutronic characteristics (effective multiplication factor, fission reaction rate), which is caused by uncertainties in initial data due to technological tolerances, are compared (in the first case) to the published results obtained using the precision MCNP5 code and (in the second case) to those obtained by means of the RADAR engineering program. A goodmore » agreement of results is achieved for all cases.« less
Authors:
 [1]
  1. National Research Center Kurchatov Institute (Russian Federation)
Publication Date:
OSTI Identifier:
22471965
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; ARRAY PROCESSORS; BENCHMARKS; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CRITICALITY; FISSION; FUEL ASSEMBLIES; M CODES; MONTE CARLO METHOD; MULTIPLICATION FACTORS; REACTION KINETICS; TRANSPORT THEORY; WWER TYPE REACTORS