Plutonium Signatures in Molten-Salt Reactor Off-Gas Tank and Safeguards Considerations

Author:

Dunkle Nicholas1ORCID,Wheeler Alex1,Richardson Jarod1,Bogetic Sandra1,Chvala Ondrej12ORCID,Skutnik Steven E.13

Affiliation:

1. Department of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996, USA

2. Department of Mechanical Engineering, University of Texas, Austin, TX 78712, USA

3. Oak Ridge National Laboratory, Oak Ridge, TN 37996, USA

Abstract

Fluid-fueled molten-salt reactors (MSRs) are actively being developed by several companies, with plans to deploy them internationally. The current IAEA inspection tools are largely incompatible with the unique design features of liquid fuel MSRs (e.g., the complex fuel chemistry, circulating fuel inventory, bulk accountancy, and high radiation environment). For these reasons, safeguards for MSRs are seen as challenging and require the development of new techniques. This paper proposes one such technique through the observation of the reactor’s off-gas. Any reactor design using low-enriched uranium will build up plutonium as the fuel undergoes burnup. Plutonium has different fission product yields than uranium. Therefore, a shift in fission product production is expected with fuel evolution. The passive removal of certain gaseous fission products to the off-gas tank of an MSR provides a valuable opportunity for analysis without significant modifications to the design of the system. Uniquely, due to the gaseous nature of the isotopes, beta particle emissions are available for observation. The ratios of these fission product isotopes can, thus, be traced back to the relative amount and types of fissile isotopes in the core. This proposed technique represents an effective safeguards tool for bulk accountancy which, while avoiding being onerous, could be used in concert with other techniques to meet the IAEA’s timeliness goals for the detection of a diversion.

Funder

United States Department of Energy

Oak Ridge National Laboratory

Publisher

MDPI AG

Subject

General Medicine

Reference37 articles.

1. Dunkle, N., and Chvala, O. (2021, January 21–26). Safeguards By Design Considerations For Modular Molten Salt Reactors. Proceedings of the INMM/ESARDA Joint Annual Meeting, INMM, Online. Available online: https://resources.inmm.org/annual-meeting-proceedings/safeguards-design-considerations-modular-molten-salt-reactors.

2. Leppanen, J. (2023, May 02). Serpent—A Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code. Available online: https://usermanual.wiki/Document/Serpentmanual.1526141273/view.

3. Wheeler, A.M., Chvála, O., and Skutnik, S. (2021). Signatures of plutonium diversion in Molten Salt Reactor dynamics. Ann. Nucl. Energy, 160.

4. Dunkle, N.J., Richardson, J., Pathirana, V., Wheeler, A., Chvala, O., and Skutnik, S.E. (2022). NERTHUS Thermal Spectrum Molten Salt Reactor Neutronics and Dynamic Model. Nucl. Eng. Des., Available online: https://papers.ssrn.com/sol3/papers.cfm?abstract_id=4351209.

5. Dunkle, N., and Chvala, O. (2023). Effect of Xenon Removal Rate on Load Following in High Power Thermal Spectrum Molten-Salt Reactors (MSRs). Nucl. Eng. Des., 409, Available online: https://www.sciencedirect.com/science/article/pii/S0029549323001784.

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