Investigation of fuel rod behaviour under extended 1 burnup conditions with ROFEM fuel performance code
Creators
Description
Extending burnup is a practical way to improve the economics of water-reactor operation, via enhanced fuel utilisation and reduced spent fuel volume. A dedicated fuel behaviour modeling computer code (entitled ROFEM-1B) has been developed in order to analyse high burnup fuel performance. The code was benchmarked on an experimental data base which include a significant number of irradiation experiments performed in TRIGA-INR Pitesti research reactor. Five fuel rod behaviour during irradiation up to 50 MWd kg-1UO2-1 burnup have been analysed by the code in the framework of the first phase of the international FUMEX code exercise co-ordinated by IAEA Vienna. The input experimental data package has been prepared by IFE-OECD Halden, Norway laboratory. In the second phase of the FUMEX exercise the participants have analysed eight simplified theoretical cases. The paper presents and discuss the results obtained with ROFEM-1B in this exercise and the comparison between code predictions and experimental data
Additional details
Identifiers
- PII
- S0306454997000911;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 25
- Journal Issue
- 10
- Journal Page Range
- p. 695-708
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- Malaysia
- INIS RN
- 34039543
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- BENCHMARKS; BURNUP; EXPERIMENTAL DATA; F CODES; NUCLEAR FUELS; PERFORMANCE; R CODES; TRIGA-2-PITESTI REACTOR
- Descriptors DEC
- COMPUTER CODES; DATA; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; INFORMATION; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; NUMERICAL DATA; PULSED REACTORS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; TRIGA TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 1998 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.