Burnup performance of rock-like oxide (ROX) fuel in small pebble bed reactor with accumulative fuel loading scheme
Creators
- 1. Department of Nuclear Engineering, Tokyo Institute of Technology, 2-12-N1-19 Ookayama, Meguro-ku, Tokyo 152-8550 (Japan)
- 2. Laboratory for Advanced Nuclear Energy, Institute of Innovative Research, Tokyo Institute of Technology, 2-12-N1-19 Ookayama, Meguro-ku, Tokyo 152-8550 (Japan)
Description
Highlights: • Burnup performance using ROX fuel in PBR with accumulative fuel loading scheme was analyzed. • Initial excess reactivity was suppressed by reducing 235U enrichment in the startup condition. • Negative temperature coefficient was achieved in all condition of PBR with accumulative fuel loading scheme using ROX fuel. • Core lifetime of PBR with accumulative fuel loading scheme using ROX fuel was shorter than with UO2 fuel. • In PBR with accumulative fuel loading scheme using ROX fuel, achieved discharged burnup can be as high as that for UO2 fuel. - Abstract: The Japan Atomic Energy Agency (JAEA) has proposed rock-like oxide (ROX) fuel as a new, once-through type fuel concept. Here, burnup performance using ROX fuel was simulated in a pebble bed reactor with an accumulative fuel loading scheme. The MVP-BURN code was used to simulate the burnup calculation. Fuel of 5 g-HM/pebble with 20% 235U enrichment was selected as the optimum composition. Discharged burnup could reach up to 218 GWd/t, with a core lifetime of about 8.4 years. However, high excess reactivity occurred in the initial condition. Initial fuel enrichment was therefore reduced from 20% to 4.65% to counter the initial excess reactivity. The operation period was reduced by the decrease of initial fuel enrichment, but the maximum discharged burnup was 198 GWd/t. Burnup performance of ROX fuel in this reactor concept was compared with that of UO2 fuel obtained previously. Discharged burnup for ROX fuel in the PBR with an accumulative fuel loading scheme was as high as UO2 fuel. Maximum power density could be lowered by introducing ROX fuel compared to UO2 fuel. However, PBR core lifetime was shorter with ROX fuel than with UO2 fuel. A negative temperature coefficient was achieved for both UO2 and ROX fuels throughout the operation period.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2017.04.019Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2017.04.019;
- PII
- S0306-4549(16)30430-3;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 107
- Journal Page Range
- p. 110-118
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48086729
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S29: ENERGY PLANNING, POLICY AND ECONOMY;
- Descriptors DEI
- BURNUP; COMPARATIVE EVALUATIONS; ENRICHMENT; JAEA; LIFETIME; NUCLEAR FUELS; PEBBLE BED REACTORS; PERFORMANCE; POWER DENSITY; REACTOR CORES; REACTOR OPERATION; TEMPERATURE COEFFICIENT; URANIUM 235; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CHALCOGENIDES; ENERGY SOURCES; EVALUATION; EVEN-ODD NUCLEI; FUELS; GAS COOLED REACTORS; HEAVY NUCLEI; HOMOGENEOUS REACTORS; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; JAPANESE ORGANIZATIONS; MATERIALS; MINUTES LIVING RADIOISOTOPES; NATIONAL ORGANIZATIONS; NUCLEI; OPERATION; OXIDES; OXYGEN COMPOUNDS; RADIOISOTOPES; REACTIVITY COEFFICIENTS; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; SOLID HOMOGENEOUS REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM COMPOUNDS; URANIUM ISOTOPES; URANIUM OXIDES; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.