Burn-up credit criticality safety benchmark phase VII - UO2 fuel: study of spent fuel compositions for long-term disposal
Description
After spent nuclear fuel (SNF) is discharged from a nuclear reactor, fuel composition and reactivity continue to vary as a function of time due to the decay of unstable nuclides. Accurate predictions of the concentrations of long-lived radionuclides in SNF, which represent a significant potential hazard to human beings and to the environment over a very long period, are particularly necessary for radiological dose assessments. This report assesses the ability of existing computer codes and associated nuclear data to predict isotopic compositions and their corresponding neutron multiplication factor (keff) values for pressurised-water-reactor (PWR) UO2 fuel at 50 GWd/MTU burn-up in a generic spent fuel cask configuration. Fuel decay compositions and keff values have been calculated for 30 post-irradiation time steps out to one million years
Additional details
Publishing Information
- Publisher
- Organisation for Economic Co-Operation and Development - Nuclear Energy Agency
- Imprint Place
- Issy-les-Moulineaux (France)
- ISBN
- 978-92-64-99172-9
- Imprint Pagination
- 180 p.
INIS
- Country of Publication
- France
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 43056211
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S97: MATHEMATICAL METHODS AND COMPUTING; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Descriptors DEI
- BENCHMARKS; BURNUP; COMPUTER CODES; COMPUTERIZED SIMULATION; CRITICALITY; CROSS SECTIONS; DATA COVARIANCES; DECAY; FISSION PRODUCTS; FUEL ASSEMBLIES; HALF-LIFE; ISOTOPE RATIO; MATHEMATICAL SOLUTIONS; MULTIPLICATION FACTORS; NUCLEAR DATA COLLECTIONS; PWR TYPE REACTORS; SPENT FUEL CASKS; SPENT FUELS; TIME DEPENDENCE
- Descriptors DEC
- CASKS; CONTAINERS; DIMENSIONLESS NUMBERS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; ISOTOPES; MATERIALS; NUCLEAR FUELS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 23 refs.