Application of Safeguards to a Molten Salt Reactor

Year
2018
Author(s)
Evans D. Kitcher - Texas A&M University, Center for Nuclear Security Science and Policy Initiatives
Jeremy Osborn - Texas A&M University, Department of Nuclear Engineering
Mateusz Marciniak - Texas A&M University, Department of Nuclear Engineering
Gerardo Garcia - Texas A&M University, Department of Nuclear Engineering
Bryan Batista - Texas A&M University, Department of Nuclear Engineering
Sunil Chirayath - Texas A&M University, Center for Nuclear Security Science and Policy Initiatives
Abstract
Across the globe, variations of the molten salt reactor (MSR) design are being developed for commercialization as part of the push to utilize Generation IV reactor designs to meet the world’s future energy needs. In this study, conventional safeguards strategies will be used to develop a nuclear material accountancy plan for a molten salt reactor (MSR) that uses a low-enriched uranium (LEU) driver core with a thorium blanket for breeding.Safeguards strategies consist of systems of nuclear material accountancy, containment, surveillance, and other measures to meet detection goals. The specific implementation of these strategies is unique to each facility, with detailed inspection goals, procedures, and measures specified in subsidiary arrangements and facility attachments. MSR designs require a different approach from conventional commercial reactors because the fuel is present as a bulk flow of fuel salt material. At present, there is also a lack of IAEA safeguards guidelines on MSR designs. This is because most MSR designs are still at an early stage of the engineering design process.The objective of the study is to apply traditional non-proliferation and safeguards strategies to the chosen reactor design and determine if the traditional approach can be used to comply with International Atomic Energy Agency guidelines. The goal would be to determine the nuclear material inventory for a given material balance period (MBP), for example one year, and to confirm that the probability of the material being lost or stolen from the facility is null. To achieve this, a generic MSR design will be developed and nuclear material accountancy applied. This will include the creation of material balance areas (MBAs) and selection of material balance periods (MBPs) based on the types of material present and throughput of the facility. Calculated nuclear materials balance (NMB) figures will reflect differences between the inventory of nuclear materials such as bulk thorium and bulk uranium.