Evaluation of the criticality and reaction rate benchmark experiments utilizing UO2F2 aqueous solution of intermediate enrichment in spherical geometry at ORNL
Creators
- 1. Faculty of Mathematics and Physics, University of Ljubljana, Jadranska ulica 19, SI-1000, Ljubljana (Slovenia)
- 2. Jožef Stefan Institute, Jamova cesta 39, SI-1000, Ljubljana (Slovenia)
- 3. Idaho National Laboratory, 1955 N. Fremont Ave., Idaho Falls, ID, 83415 (United States)
Description
An evaluation of the criticality and relative fission rate radial distribution experiments in an 69.2-cm diameter aluminium sphere filled with intermediately enriched UO2F2 aqueous solution is presented. An evaluation of the total experimental uncertainty has been performed within the framework of the International Criticality Benchmark Evaluation Project (ICSBEP) and International Reactor Physics Benchmark Evaluation Project (IRPhEP). In addition, the uncertainty due to the uncertainties in the nuclear data is evaluated in this paper. It has been determined that the highest contribution to the overall uncertainty in the effective multiplication factor keff is due to the uncertainty in the uranium enrichment (550 pcm in keff due to the 4% uncertainty in 235U enrichment). The highest experimental uncertainties in the relative fission rate profile in terms of the relative standard uncertainty (Lrs) are 0.032, 0.016, and 0.020 due to the uncertainty in guide tube diameter, filling tubes position, and detector position, respectively. It is estimated that the uncertainty in the nuclear data contributes approximately 400 pcm–1200 pcm to the uncertainty in keff depending on the covariance data library used. keff and radial fission rates have been calculated with MCNP and COG Monte Carlo neutron transport codes and have been compared to the experimental benchmark values. In general, the various Monte Carlo codes have given similar results with deviations within uncertainties.
Additional details
Identifiers
- DOI
- 10.1016/j.pnucene.2018.10.024;
- PII
- S0149197018302762;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 111
- Journal Page Range
- p. 97-108
- ISSN
- 0149-1970
- CODEN
- PNENDE
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 55054809
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AQUEOUS SOLUTIONS; FISSION; GUIDE TUBES; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NEUTRON TRANSPORT; ORNL; REACTOR PHYSICS; URANIUM 235; URANYL FLUORIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CALCULATION METHODS; DIMENSIONLESS NUMBERS; DISPERSIONS; EVEN-ODD NUCLEI; FLUORIDES; FLUORINE COMPOUNDS; HALIDES; HALOGEN COMPOUNDS; HEAVY NUCLEI; HOMOGENEOUS MIXTURES; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MINUTES LIVING RADIOISOTOPES; MIXTURES; NATIONAL ORGANIZATIONS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR REACTIONS; NUCLEI; PHYSICS; RADIATION TRANSPORT; RADIOISOTOPES; SOLUTIONS; SPONTANEOUS FISSION RADIOISOTOPES; TUBES; URANIUM COMPOUNDS; URANIUM ISOTOPES; URANYL COMPOUNDS; URANYL HALIDES; US AEC; US DOE; US ERDA; US ORGANIZATIONS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2018 Elsevier Ltd. All rights reserved.