KRITZ-2 benchmark calculations using different nuclear data libraries
Creators
- 1. SCK-CEN, Boeretang 200, B-2400 Mol (Belgium)
- 2. OECD/NEA, Le Saint-Germain, 12 Bd des Iles, 92130 Issy-les-Moulineaux (Nuclear Energy Agency of the OECD (NEA))
- 3. Korea Atomic Energy Research Institute (KAERI), Dukjin-dong 150, Yusong, Daejon, 305-600 (Korea, Republic of)
Description
A set of KRITZ-2 experiments with light water moderated lattices with uranium rods and mixed-oxide rods, at room and elevated temperatures, were performed in the early 1970's. Using the results of these experiments, an international benchmark was developed and launched by the OECD/NEA in co-operation with ORNL. This paper presents the results obtained from two versions of MCNP calculations (4C and 4B) for the KRITZ-2 experiments, using three different nuclear data libraries (JEF-2.2, ENDF/B-VI.5 and JENDL-3.2). For the MCNP library generation, the nuclear data processing system NJOY (version 97.114) is used. For both sets of calculations, the three KRITZ-2 cores are explicitly modelled in 3-D geometry. The linear thermal expansion coefficients given in the specification are used to determine the dimensions of the core geometry, the material densities, and the atomic number densities of the materials at high temperatures. The calculated results are compared with experimental results for both keff and pin powers in different cores (two UO2- and one MOX-fuelled cores). The influence of the nuclear data libraries on calculated results are examined. The calculated keff results show a strong dependence on the basic data libraries used. The calculated pin powers are in general in good agreement with the experimental values within ±2% of discrepancy for most of the fuel pin positions. (author)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Pagination
- 12 p.
Conference
- Title
- International Conference on the New Frontiers of Nuclear Technology: Reactor Physics, Safety and High-Performance Computing
- Acronym
- Physor 2002
- Dates
- 7-10 Oct 2002
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 55004437
- Subject category
- S97: MATHEMATICAL METHODS AND COMPUTING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATOMIC NUMBER; BENCHMARKS; DATA PROCESSING; FUEL PINS; LIBRARIES; MIXED OXIDE FUELS; NUCLEAR DATA COLLECTIONS; THERMAL EXPANSION; VISIBLE RADIATION
- Descriptors DEC
- ELECTROMAGNETIC RADIATION; ENERGY SOURCES; EXPANSION; FUEL ELEMENTS; FUELS; MATERIALS; NUCLEAR FUELS; PROCESSING; RADIATIONS; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS
Optional Information
- Notes
- 5 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)