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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.
Seungsu Yuk, Nam Zin Cho
Nuclear Science and Engineering | Volume 184 | Number 2 | October 2016 | Pages 151-167
Technical Paper | doi.org/10.13182/NSE15-128
Articles are hosted by Taylor and Francis Online.
Two two-dimensional/one-dimensional (2-D/1-D) methods, fusion and hybrid, have been developed and reported in the literature to deal with three-dimensional (3-D) heterogeneous reactor problems and to avoid direct 3-D transport calculations. The 2-D/1-D fusion method transforms a 3-D transport problem into 2-D and 1-D transport problems that have a smaller computational burden than the original problem. The hybrid method uses an additional diffusion (or SP3) approximation in the axial direction to enhance the efficiency of the calculation.
This paper presents and compares the stability and the accuracy of the two methods. To this end, a 2-D transport problem is considered by reducing one dimension in the radial direction, leading to 1-D/1-D fusion or hybrid method. Fourier stability analysis is used to study the stability and the convergence behaviors of the two methods. With respect to accuracy, the two methods are compared via numerical solutions on a typical 2-D reactor problem. The results indicate that the fusion method is stable and gives a very accurate transport solution. On the other hand, the hybrid method requires a stabilizing scheme, and the diffusion approximation in the axial calculation causes significant errors.