Monte Carlo Simulation of the TRIGA Mark II Benchmark Experiment with Burned Fuel
Description
Monte Carlo calculations of a criticality experiment with burned fuel on the TRIGA Mark II research reactor are presented. The main objective was to incorporate burned fuel composition calculated with the WIMSD4 deterministic code into the MCNP4B Monte Carlo code and compare the calculated keff with the measurements. The criticality experiment was performed in 1998 at the ''Jozef Stefan'' Institute TRIGA Mark II reactor in Ljubljana, Slovenia, with the same fuel elements and loading pattern as in the TRIGA criticality benchmark experiment with fresh fuel performed in 1991. The only difference was that in 1998, the fuel elements had on average burnup of ∼3%, corresponding to 1.3-MWd energy produced in the core in the period between 1991 and 1998. The fuel element burnup accumulated during 1991-1998 was calculated with the TRIGLAV in-house-developed fuel management two-dimensional multigroup diffusion code. The burned fuel isotopic composition was calculated with the WIMSD4 code and compared to the ORIGEN2 calculations. Extensive comparison of burned fuel material composition was performed for both codes for burnups up to 20% burned 235U, and the differences were evaluated in terms of reactivity. The WIMSD4 and ORIGEN2 results agreed well for all isotopes important in reactivity calculations, giving increased confidence in the WIMSD4 calculation of the burned fuel material composition. The keff calculated with the combined WIMSD4 and MCNP4B calculations showed good agreement with the experimental values. This shows that linking of WIMSD4 with MCNP4B for criticality calculations with burned fuel is feasible and gives reliable results
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 137
- Journal Issue
- 3
- Journal Page Range
- p. 169-180
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 38002164
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; BURNUP; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CRITICALITY; FUEL ELEMENTS; FUEL MANAGEMENT; ISOTOPE RATIO; MONTE CARLO METHOD; REACTIVITY; RESEARCH REACTORS; SPENT FUELS; TRIGA-2 REACTOR; TWO-DIMENSIONAL CALCULATIONS; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; DIMENSIONLESS NUMBERS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EVALUATION; EVEN-ODD NUCLEI; FUELS; HEAVY NUCLEI; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; INTERNAL CONVERSION RADIOISOTOPES; IRRADIATION REACTORS; ISOMERIC TRANSITION ISOTOPES; ISOTOPE PRODUCTION REACTORS; ISOTOPES; MANAGEMENT; MATERIALS; MINUTES LIVING RADIOISOTOPES; NUCLEAR FUELS; NUCLEAR MATERIALS MANAGEMENT; NUCLEI; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; SOLID HOMOGENEOUS REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; THERMAL REACTORS; TRIGA TYPE REACTORS; URANIUM ISOTOPES; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/