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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.
K. Forsberg, Ning He, A. R. Massih
Nuclear Science and Engineering | Volume 122 | Number 1 | January 1996 | Pages 142-150
Technical Note | doi.org/10.13182/NSE96-A28555
Articles are hosted by Taylor and Francis Online.
Distribution of some important fuel rod performance parameters, internal rod pressure, and fission gas release in a boiling water reactor are studied using the quasi-Monte Carlo (QMC) probabilistic method. Rod power histories and important fabrication parameters are considered. The deterministic fuel performance code STAV6 together with a QMC pre- and postprocessor are used in the analysis. The convergence rate of the QMC method is considerably higher than the standard Monte Carlo method, which saves a substantial amount of computer time. Asymptotically, the error for QMC is proportional to 1/N, and for Monte Carlo, it is essentially proportional to 1/ where N is the number of calculations (computer runs). Principles of the QMC method are discussed, and an algorithm to generate such data is outlined.