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ORIGINAL RESEARCH article

Front. Nucl. Eng.

Sec. Radioactive Waste Management

This article is part of the Research TopicAdvanced Modeling Techniques in Radioactive Waste DisposalView all 6 articles

Identification of safety-relevant radionuclides for performance assessment modeling

Provisionally accepted
Stefan  FinsterleStefan Finsterle1*Michael  J. Hannon Jr.Michael J. Hannon Jr.2Jesse  SloaneJesse Sloane3
  • 1Finsterle GeoConsulting, LLC, Kensington, United States
  • 2Hannon Clean Energy LLC, Bloomington, Indiana, United States
  • 3Deep Isolation, Berkeley, California, United States

The final, formatted version of the article will be published soon.

We propose, apply, and verify a screening approach for the selection of safety-relevant radionuclides that should be tracked in models assessing the performance of geologic repositories for the disposal of spent nuclear fuel and high-level radioactive wastes. Starting with a comprehensive list of radionu-clides present in the waste form, a multi-step down-selection process evaluates each isotope's potential relative contribution to the total peak exposure dose, which is a surrogate metric for overall repository safety. In the first screening step, only basic, readily available characteristics of a radionuclide are needed, such as its inventory, half-life, specific activity, and dose coefficient. In the second step, the radionuclide's transport time from the repository to the accessible environment is estimated based on factors affecting its mobility and retardation. By adjusting the screening threshold, the number of radionuclides considered potentially safety-relevant can be changed, thus yielding a larger or smaller (more or less conservative) set of radioisotopes being tracked in the performance assessment model, as warranted by the stage of repository development. We exercise the proposed screening approach for a particular waste form—spent nuclear fuel assemblies—and two disposal pathways—deep horizontal and vertical borehole repositories. An integrated performance assessment model is then used to simulate the migration of a considerably larger set of radionuclides from the disposal canisters to the land surface. The acceptably small difference in peak dose calculated with the comprehensive and reduced set of radionuclides indicates the appropriateness of the proposed screening approach.

Keywords: ITOUGH2, Performance assessment model, Radioactive waste disposal, radionuclide source-term model, Vitrified waste, Waste degradation

Received: 14 Jan 2026; Accepted: 06 Feb 2026.

Copyright: © 2026 Finsterle, Hannon Jr. and Sloane. This is an open-access article distributed under the terms of the Creative Commons Attribution License (CC BY). The use, distribution or reproduction in other forums is permitted, provided the original author(s) or licensor are credited and that the original publication in this journal is cited, in accordance with accepted academic practice. No use, distribution or reproduction is permitted which does not comply with these terms.

* Correspondence: Stefan Finsterle

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