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Title: Evaluation of design parameters for TRISO-coated fuel particles to establish manufacturing critical limits using PARFUME

Journal Article · · Journal of Nuclear Materials
 [1];  [1];  [1];  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
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The success of modular high temperature gas-cooled reactors is highly dependent on the performance of the tristructural-isotopic (TRISO) coated fuel particle and the quality to which it can be manufactured. During irradiation, TRISO-coated fuel particles act as a pressure vessel to contain fission gas and mitigate the diffusion of fission products to the coolant boundary. The fuel specifications place limits on key attributes to minimize fuel particle failure under irradiation and postulated accident conditions. PARFUME (an integrated mechanistic coated particle fuel performance code developed at the Idaho National Laboratory) was used to calculate fuel particle failure probabilities. By systematically varying key TRISO-coated particle attributes, failure probability functions were developed to understand how each attribute contributes to fuel particle failure. Critical manufacturing limits were calculated for the key attributes of a low enriched TRISO-coated nuclear fuel particle with a kernel diameter of 425 μm. As a result, these critical manufacturing limits identify ranges beyond where an increase in fuel particle failure probability is expected to occur.

Research Organization:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
1251426
Alternate ID(s):
OSTI ID: 1396698
Report Number(s):
INL/JOU-15-34392; PII: S0022311515303354
Journal Information:
Journal of Nuclear Materials, Vol. 469, Issue C; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 18 works
Citation information provided by
Web of Science

References (6)

High-Temperature Gas-Cooled Reactor Fuel Pressure Vessel Performance Models journal March 1985
Considerations pertaining to the achievement of high burn-ups in HTR fuel journal April 2002
Fabrication of uranium oxycarbide kernels and compacts for HTR fuel journal October 2012
Statistical approach and benchmarking for modeling of multi-dimensional behavior in TRISO-coated fuel particles journal April 2003
Consideration of the effects on fuel particle behavior from shrinkage cracks in the inner pyrocarbon layer journal June 2001
Consideration of the effects of partial debonding of the IPyC and particle asphericity on TRISO-coated fuel behavior journal September 2004

Cited By (1)

A novel method to inspect coating thickness of tristructural isotropic fuel particles journal February 2019

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Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
inner pyrolytic carbon (IPyC)
TRISO
silicon carbide (SiC)
outer pyrolytic carbon (OPyC)
PARFUME
Advanced Gas Reactor (AGR)
Advanced Test Reactor (ATR)