TRISO fuel performance analysis: Uncertainty quantification toward optimization

Baghdasaryan, Nairi; Jiang, Wen; Hales, Jason D.; Kozlowski, Tomasz; Krajewska, Zuzanna

doi:10.1016/j.nucengdes.2023.112401

TRISO fuel performance analysis: Uncertainty quantification toward optimization

Journal Article · Thu Jun 01 00:00:00 EDT 2023 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2023.112401· OSTI ID:1988112

^[1]; ^[2]; ^[2]; ^[1]; Krajewska, Zuzanna ^[1]

National Centre for Nuclear Research, Otwock (Poland)
Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Tri-structural isotropic (TRISO) fuel particles are a fuel form being considered for potential use in next-generation nuclear reactors (i.e., high-temperature gas-cooled reactors). Though the TRISO fuel manufacturing process has continually advanced in recent years, particle comparisons still reveal statistical variations and uncertainties in terms of geometric configurations and material properties. Given that the physical processes ongoing in TRISO fuel particles during reactor operation are highly correlated with each other, a small degree of uncertainty in one model may lead to significant uncertainty in another. This makes appropriate uncertainty quantification of TRISO fuel particles essential. However, one may wonder about the extent to which the current version of TRISO particles has been optimized, and whether any room remains for further improvements. This paper quantifies TRISO fuel performance model uncertainties that stem from geometric and material data. For this analysis, the BISON code was used, and the Advanced Gas Reactor (AGR)-2 experiment served as a reference case. A total of 10⁵ calculations was performed for the uncertainty and optimization analysis, altering the geometric and material data within their uncertainty range. Lastly, the optimization potential of TRISO particles is evaluated from a fuel performance perspective.

Research Organization:: Idaho National Laboratory (INL), Idaho Falls, ID (United States); Polish National Research and Development Center (NCBR), Otwock (Poland)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1988112

Report Number(s):: INL/JOU-23-72321-Revision-0

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Vol. 410; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (10)

Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part I: Lattice benchmarking, cycle length, and reactivity coefficients Brown, Nicholas R.; Ludewig, Hans; Aronson, Arnold Annals of Nuclear Energy, Vol. 62 https://doi.org/10.1016/j.anucene.2013.05.025	journal	December 2013
Microencapsulated fuel technology for commercial light water and advanced reactor application Terrani, Kurt A.; Snead, Lance L.; Gehin, Jess C. Journal of Nuclear Materials, Vol. 427, Issue 1-3, p. 209-224 https://doi.org/10.1016/j.jnucmat.2012.05.021	journal	August 2012
The study of irradiation-induced failure behavior for the TRISO-coated fuel particle in HTGR Li, Rong; Liu, Bing; Verfondern, Karl Journal of Nuclear Materials, Vol. 516 https://doi.org/10.1016/j.jnucmat.2019.01.029	journal	April 2019
Efficient high-fidelity TRISO statistical failure analysis using Bison: Applications to AGR-2 irradiation testing Jiang, Wen; Singh, Gyanender; Hales, Jason D. Journal of Nuclear Materials, Vol. 562 https://doi.org/10.1016/j.jnucmat.2022.153585	journal	April 2022
Utilization of TRISO fuel with reactor grade plutonium in CANDU reactors Şahin, Sümer; Şahin, Hacı Mehmet; Acır, Adem Nuclear Engineering and Design, Vol. 240, Issue 8 https://doi.org/10.1016/j.nucengdes.2010.04.008	journal	August 2010
Pressure buildup analysis of TRISO-coated fuel particles Baghdasaryan, Nairi; Kozlowski, Tomasz Nuclear Engineering and Design, Vol. 380 https://doi.org/10.1016/j.nucengdes.2021.111279	journal	August 2021
Conceptual core design of an innovative small PWR utilizing fully ceramic microencapsulated fuel Dai, Xiang; Cao, Xinrong; Yu, Shihe Progress in Nuclear Energy, Vol. 75 https://doi.org/10.1016/j.pnucene.2014.04.010	journal	August 2014
BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms Williamson, Richard L.; Hales, Jason D.; Novascone, Stephen R. Nuclear Technology https://doi.org/10.1080/00295450.2020.1836940	journal	March 2021
Review of Progress in Coated Fuel Particle Performance Analysis Baghdasaryan, Nairi; Kozlowski, Tomasz Nuclear Science and Engineering, Vol. 194, Issue 3 https://doi.org/10.1080/00295639.2019.1686882	journal	November 2019
The Performance of High-Temperature Reactor Fuel Particles at Extreme Temperatures Nabielek, Heinz; Schenk, Werner; Heit, Werner Nuclear Technology, Vol. 84, Issue 1 https://doi.org/10.13182/NT89-A34196	journal	January 1989

Similar Records

Simulation of a TRISO MiniFuel irradiation experiment with data-informed uncertainty quantification

Journal Article · Mon Jan 23 19:00:00 EST 2023 · Nuclear Engineering and Design · OSTI ID:1923167

BISON TRISO Modeling Advancements and Validation to AGR-1 Data

Technical Report · Mon Sep 14 00:00:00 EDT 2020 · OSTI ID:1711423

Bison Verification and Validation Activities for TRISO

Conference · Thu Nov 02 00:00:00 EDT 2023 · OSTI ID:2205323

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Geometrical and material properties
Optimization
TRISO fuel
Uncertainty quantification

TRISO fuel performance analysis: Uncertainty quantification toward optimization

Citation Formats

References (10)

Similar Records

Related Subjects