Assessment of CASMO-4 predictions of the isotopic inventory of high burn-up MOX fuel
Creators
- 1. Paul Scherrer Inst., Villigen PSI, CH-5232 (Switzerland)
- 2. Swiss Federal Inst. of Technology (EPFL), Lausanne (Switzerland)
Description
The current paper presents an assessment of the depletion model in CASMO-4 based on highly-burnt MOX fuel data from the Programme ARIANE. Isotopic compositions calculated with CASMO-4 for a sample irradiated for 6 cycles in the Swiss PWR Beznau-1 have been compared with experimental data from the PSI and SCK.CEN radio-chemical laboratories. Both a 1-D pin-cell and a 2-D fuel-assembly model have been used, together with detailed and burn-up averaged irradiation histories. The results obtained (a) show that predictions for the most important actinides have errors below 10%, (b) highlight problems with Am and Eu isotopes, and (c) indicate experimental inaccuracies probably linked to the measurement techniques for 129I and some metallic fission products. Additional studies, focused on refined pin-cell treatment, have found that such modeling effects can be significant for the prediction of some actinides, e.g. Pu, Cm and Am. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448683-7
- Imprint Pagination
- 10 p.
Conference
- Title
- The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
- Acronym
- PHYSOR 2004
- Dates
- 25-29 Apr 2004
- Place
- Chicago, IL (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 42097607
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ACTINIDES; BEZNAU-1 REACTOR; BURNUP; C CODES; COMPUTERIZED SIMULATION; EUROPIUM ISOTOPES; EXPERIMENTAL DATA; FISSION PRODUCTS; FUEL ASSEMBLIES; FUEL CYCLE; FUEL PINS; IODINE 129; ISOTOPE RATIO; MIXED OXIDE FUELS; NEUTRON TRANSPORT; REACTOR LATTICE PARAMETERS; TWO-DIMENSIONAL CALCULATIONS
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; COMPUTER CODES; DATA; DIMENSIONLESS NUMBERS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; INFORMATION; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IODINE ISOTOPES; ISOTOPES; MATERIALS; METALS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FUELS; NUCLEI; NUMERICAL DATA; ODD-EVEN NUCLEI; POWER REACTORS; PWR TYPE REACTORS; RADIATION TRANSPORT; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SIMULATION; SOLID FUELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 5 refs.