Published July 7, 2000
| Version v1
Journal article
Modeling of fission gas release in MOX fuel considering the distribution of Pu-rich particles
- 1. Korea Atomic Energy Research Institute, Daejon (Korea, Republic of)
Description
In this paper, a fission gas release model for MOX fuel has been developed for the analysis of the effect of Pu heterogeneity on gas release by considering the distribution of Pu-rich particles. This model is an extension of the previous one which used the assumption that all Pu-rich particles are of the same size
Additional details
Identifiers
- DOI
- 10.1063/1.1292260;
Publishing Information
- Journal Title
- AIP Conference Proceedings
- Journal Volume
- 532
- Journal Issue
- 1
- Journal Page Range
- p. 205-207
- ISSN
- 0094-243X
- CODEN
- APCPCS
Conference
- Title
- Plutonium futures - the science
- Acronym
- Topical conference on plutonium and actinides
- Dates
- 10-13 Jul 2000
- Place
- Santa Fe, NM (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35046326
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DISTRIBUTION; FISSION PRODUCTS; GASEOUS WASTES; MIXED OXIDE FUELS; PARTICLE SIZE; PLUTONIUM DIOXIDE; POWDERS; RADIOACTIVE WASTES; SIMULATION; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; FUELS; ISOTOPES; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; RADIOACTIVE MATERIALS; REACTOR MATERIALS; SIZE; SOLID FUELS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; WASTES
Optional Information
- Notes
- (c) 2000 American Institute of Physics.