DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

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

Abstract

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]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1251426
Alternate Identifier(s):
OSTI ID: 1396698
Report Number(s):
INL/JOU-15-34392
Journal ID: ISSN 0022-3115; PII: S0022311515303354
Grant/Contract Number:  
AC07-05ID14517
Resource 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
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)

Citation Formats

Skerjanc, William F., Maki, John T., Collin, Blaise P., and Petti, David A. Evaluation of design parameters for TRISO-coated fuel particles to establish manufacturing critical limits using PARFUME. United States: N. p., 2015. Web. doi:10.1016/j.jnucmat.2015.11.027.
Skerjanc, William F., Maki, John T., Collin, Blaise P., & Petti, David A. Evaluation of design parameters for TRISO-coated fuel particles to establish manufacturing critical limits using PARFUME. United States. https://doi.org/10.1016/j.jnucmat.2015.11.027
Skerjanc, William F., Maki, John T., Collin, Blaise P., and Petti, David A. Wed . "Evaluation of design parameters for TRISO-coated fuel particles to establish manufacturing critical limits using PARFUME". United States. https://doi.org/10.1016/j.jnucmat.2015.11.027. https://www.osti.gov/servlets/purl/1251426.
@article{osti_1251426,
title = {Evaluation of design parameters for TRISO-coated fuel particles to establish manufacturing critical limits using PARFUME},
author = {Skerjanc, William F. and Maki, John T. and Collin, Blaise P. and Petti, David A.},
abstractNote = {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.},
doi = {10.1016/j.jnucmat.2015.11.027},
journal = {Journal of Nuclear Materials},
number = C,
volume = 469,
place = {United States},
year = {Wed Dec 02 00:00:00 EST 2015},
month = {Wed Dec 02 00:00:00 EST 2015}
}

Journal Article:

Citation Metrics:
Cited by: 18 works
Citation information provided by
Web of Science

Save / Share:

Works referenced in this record:

High-Temperature Gas-Cooled Reactor Fuel Pressure Vessel Performance Models
journal, March 1985

  • Kovacs, William J.; Bongartz, Karl; Goodin, Dan T.
  • Nuclear Technology, Vol. 68, Issue 3
  • DOI: 10.13182/NT85-A33580

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

  • Miller, Gregory K.; Petti, David A.; Varacalle, Dominic J.
  • Journal of Nuclear Materials, Vol. 295, Issue 2-3
  • DOI: 10.1016/S0022-3115(01)00551-7

Consideration of the effects of partial debonding of the IPyC and particle asphericity on TRISO-coated fuel behavior
journal, September 2004


Works referencing / citing this record:

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

  • Guo, Man-shan; Yang, Xu; Zhang, Feng
  • International Journal of Energy Research, Vol. 43, Issue 6
  • DOI: 10.1002/er.4392