Modeling molybdeneum-99 production in molten salt reactors

Cornejo, Luke R.; Betzler, Benjamin R.; Myhre, Kristian; McFarlane, Joanna

doi:10.1016/j.nucengdes.2021.111243

Modeling molybdeneum-99 production in molten salt reactors

Journal Article · Sat May 08 00:00:00 EDT 2021 · Nuclear Engineering and Design

DOI:https://doi.org/10.1016/j.nucengdes.2021.111243· OSTI ID:1784153

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Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Molten salt reactors (MSRs) are being investigated as a possible source of ⁹⁹Mo for medical uses. This paper describes computational modeling being performed to determine the feasibility for use of several MSR concepts in ⁹⁹Mo production: the Molten Salt Breeder Reactor (MSBR), the Molten Salt Demonstration Reactor (MSDR), and the Molten Salt Reactor Experiment (MSRE). This modeling is accomplished with SCALE/TRITON using a three-mixture system and estimated removal terms. Results showed that the MSBR, MSDR and MSRE were capable of supplying an estimated 35,800,000, 13,700,000, and 132,000 six-day Ci/week of ⁹⁹Mo, respectively, which is far more than the global demand. In conclusion, a range of operating parameters has been determined in which each reactor type is expected to have sufficient production capability to meet global demand.

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Security

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1784153

Journal Information:: Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: August Vol. 379; ISSN 0029-5493

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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