TIMCOAT: An Integrated Fuel Performance Model for Coated Particle Fuel
- 1. Massachusetts Institute of Technology (United States)
Description
An integrated fuel performance model for coated particle fuel has been developed to comprehensively study the behavior of TRISO-coated fuel. Modeling of both pebble-bed and prismatic configurations is possible. In the case of the pebble-bed concept, refueling of pebbles is simulated to account for the nonuniform environment in the reactor core and history-dependent particle behavior. Monte Carlo sampling of particles is employed in fuel failure prediction to capture the statistical features of dimensions; material properties; and, in the case of the pebble-bed concept, the statistical nature of the refueling process. An advanced fuel failure model has been developed based on a probabilistic fracture mechanics approach. The mechanical analysis includes effects of anisotropic irradiation-induced dimensional changes and isotropic irradiation-induced creep, and the fluence-dependent Poisson ratio in irradiation creep. The stress analysis is benchmarked against the calculations of Japanese High Temperature Test Reactor (HTTR) first-loading fuel and finite element result on one case performed by the Idaho National Engineering and Environmental Laboratory. The failure model predictions are compared with NPR1, NPR2, and NPR1A capsule irradiation data. The model results compare very favorably with postirradiation examination results both in terms of failure probability, number of failed particles, and Kr85m R/B evolution during irradiation
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 148
- Journal Issue
- 1
- Journal Page Range
- p. 68-96
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 38011730
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- CREEP; FAILURES; FINITE ELEMENT METHOD; FRACTURE MECHANICS; FUEL PARTICLES; HTTR REACTOR; INEEL; IRRADIATION; IRRADIATION CAPSULES; KRYPTON 85; MONTE CARLO METHOD; NUCLEAR FUELS; PERFORMANCE; POST-IRRADIATION EXAMINATION; PRISMATIC CONFIGURATION; PROBABILISTIC ESTIMATION; REACTOR CORES; STRESS ANALYSIS
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CALCULATION METHODS; CONFIGURATION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EVEN-ODD NUCLEI; EXPERIMENTAL REACTORS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HOURS LIVING RADIOISOTOPES; HTGR TYPE REACTORS; INTERMEDIATE MASS NUCLEI; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; KRYPTON ISOTOPES; MATERIALS; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; MECHANICS; MICROSECONDS LIVING RADIOISOTOPES; NATIONAL ORGANIZATIONS; NUCLEI; NUMERICAL SOLUTION; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; US DOE; US ORGANIZATIONS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/