Published March 2015 | Version v1
Journal article Metadata-only

Comparative validation of Monte Carlo codes for the conversion of a research reactor

Creators

  • 1. National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), 31 Kashirskoe shosse, 115409 Moscow (Russian Federation)
  • 2. GTRI Program, Nuclear Engineering Division, Argonne National Laboratory, 9700 Cass Avenue, Argonne, IL 60439 (United States)
  • 3. Research and Development, The South African Nuclear Energy Corporation (Necsa), Building 1900, P.O. Box 582, 0001 Pretoria (South Africa)

Description

Highlights: • We calculate test problems for a research reactor with tube-type fuel. • The static cases and the depletion problem are examined. • We compare Monte Carlo codes: MCNP (+MCREB), MCU-PTR and SERPENT 2. • The impact of cross-section libraries on the calculated results is investigated. • A good agreement between the chosen codes results is observed. - Abstract: This paper presents the calculation results of the set of test problems for a research reactor with a tube-type low enriched uranium (LEU, 19.7 w/o, U-9%Mo) fuel and oxide high enriched uranium (HEU, 90 w/o) fuel, a light water moderator, and a beryllium reflector. The static cases and the depletion problem were examined. Calculations were performed using continuous energy Monte Carlo codes: MCNP (+MCREB for burnup calculation), MCU-PTR, and SERPENT 2. The impact of the cross-section libraries used for a particular problem on the calculated results was investigated

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2014.11.032

Additional details

Identifiers

DOI
10.1016/j.anucene.2014.11.032;
PII
S0306-4549(14)00634-3;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
77
Journal Page Range
p. 273-280
ISSN
0306-4549
CODEN
ANENDJ

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
47015007
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BERYLLIUM; BURNUP; COMPARATIVE EVALUATIONS; COMPUTER CODES; HIGHLY ENRICHED URANIUM; MONTE CARLO METHOD; NUCLEAR DATA COLLECTIONS; RESEARCH REACTORS; SLIGHTLY ENRICHED URANIUM; VALIDATION; WATER
Descriptors DEC
ACTINIDES; ALKALINE EARTH METALS; CALCULATION METHODS; ELEMENTS; ENRICHED URANIUM; EVALUATION; HYDROGEN COMPOUNDS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; OXYGEN COMPOUNDS; REACTORS; RESEARCH AND TEST REACTORS; TESTING; URANIUM

Optional Information

Copyright
Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.