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Front-end nuclear fuel supply cooperation: Turning allied interdependence into strategic advantage
The global nuclear revival, which is fueled by unprecedented demand for firm, affordable, dispatchable power for artificial intelligence and data center build-out, energy security imperatives, and climate commitments, has exposed a structural reality of the Western fuel cycle: No single allied nation currently possesses the full suite of front-end capabilities. From mining through conversion, enrichment, fabrication, and the emerging deconversion and metallization steps required for reactor fuels, capability is distributed across Canada, France, Japan, the United Kingdom, and the United States (collectively, the “Sapporo Five”), as well as a small group of close partners.
B. Richardson, J. King, A. Alajo, S. Usman, C. H. C. Giraldo
Nuclear Science and Engineering | Volume 187 | Number 1 | July 2017 | Pages 100-106
Technical Paper | doi.org/10.1080/00295639.2017.1292089
Articles are hosted by Taylor and Francis Online.
To validate an MCNP5 model of the Missouri S&T Research Reactor (MSTR), temperature and void effects on reactivity experiments were simulated and performed. We compared the keff of the modeled reactor mirroring the position of all control rods to the actual critical reactor (keff = 1.00000). In the simulation we modeled three different scenarios. In the first two scenarios, the reactor is modeled as isothermal at two different temperatures (measured experimentally near the core), and in the third scenario, we split the core into bottom and top parts and used interpolated values for the temperatures of both halves. The model predicted keff’s for the “critical reactor” between 1.00234 and 1.00248 (±0.00018) when using as temperature the experimental thermocouple readings at the top of the core and keff’s between 1.00296 to 1.00383 (±0.00018) when using the temperature of thermocouple readings at the bottom of the core. In the third experiment, a linear vertical temperature profile was included in the model (only top and bottom of the core), and the model predicted keff’s between 1.00218 and 1.00302 (±0.00018). The keff modeled and experimental values differed by as much as 0.40%. A void coefficient of the reactivity experiment was also simulated introducing a void tube in the model and the control rods made to mirror the critical experimental reactor with an identical void.