Pebbles’ Life Cycle Analysis in Salt-Cooled Pebble Bed Reactor for Enhanced Fuel Performance Assessment

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

This study explores the lifecycle of fuel pebbles in salt-cooled pebble bed reactors (PBRs), focusing on key parameters such as temperature profiles, fast fluence, and critical isotope concentrations. By employing hyper-fidelity simulation tools (HxF), the analysis provides detailed, pebble-specific histories and identifies potential outlier behaviors for the gFHR, a benchmark salt-cooled PBR. A complementary investigation examines how the diversity in pebble histories influences the diffusion of hazardous fission products under normal operating conditions. To evaluate the impact of these histories, a 1D spherical geometry diffusion solver is employed as a fuel performance model. This solver uses the pebble-wise histories as boundary conditions to simulate a representative TRISO for each pebble, enabling detailed analysis of fission product release rates. The results demonstrate the importance of accounting for time-dependent temperature and burnup histories, as the trajectory and unique conditions experienced by each pebble significantly influence the release rate of fission products from the TRISO’s kernel. This diversity in pebble histories cannot be captured by a single representative pebble model relying on core-averaged values.

Original languageEnglish
Title of host publicationProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025
PublisherAmerican Nuclear Society
Pages1322-1331
Number of pages10
ISBN (Electronic)9780894482229
DOIs
StatePublished - 2025
Event2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025 - Denver, United States
Duration: Apr 27 2025Apr 30 2025

Publication series

NameProceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025

Conference

Conference2025 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025
Country/TerritoryUnited States
CityDenver
Period04/27/2504/30/25

Funding

For the computational calculation, this research uses the Savio computational cluster resource provided by the Berkeley Research Computing program at the University of California, Berkeley (supported by the U.C. Berkeley Chancellor, Vice Chancellor for Research, and Chief Information Officer).

Keywords

  • Pebble bed reactor
  • TRISO fuel performance
  • life cycle

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