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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.
R. C. Kern, M. T. Hsu
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 141-143
Technical Note | doi.org/10.13182/NSE78-A27282
Articles are hosted by Taylor and Francis Online.
One difficulty in using the RELAP4 code is that, owing to the overspecification of the volume and junction input data for the initial conditions, a residual friction term must be defined to establish steady-state conditions. If the corresponding residual friction coefficient is out of allowable range, the calculation is terminated at the initial data checking phase. An allowable residual friction coefficient is added to the form loss coefficient and is used throughout the transient calculation. This might affect the results if the residual friction coefficient is large. However, to model a system represented by a large number of volumes and junctions, manual adjustment of the input data, such as the pressure distribution, to reduce the effect of residual terms can take a significant amount of engineering time. A procedure that allows the code to do the adjustment internally is described in this Note.