skip to main content

DOE PAGESDOE PAGES

  • DOE PAGES
  • Accepted Manuscript: Evaluation of design parameters for TRISO-coated fuel particles to establish manufacturing critical limits using PARFUME

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

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.
Authors:
 [1] ;  [1] ;  [1] ;  [1]
+ Show Author Affiliations
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Report Number(s):
INL/JOU-15-34392
Journal ID: ISSN 0022-3115; PII: S0022311515303354
Grant/Contract Number:
AC07-05ID14517
Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 469; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Research Org:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
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)
OSTI Identifier:
1251426