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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.
Stephane Cathalau, Amal Benslimane, Abdelmajid Maghnouj, Philippe Fougeras, Vladimir Ukraintsev
Nuclear Science and Engineering | Volume 121 | Number 2 | October 1995 | Pages 326-333
Technical Paper | doi.org/10.13182/NSE95-A28568
Articles are hosted by Taylor and Francis Online.
The calculation of reactor design parameters with ever higher accuracy requires constant improvement in basic nuclear data and computational techniques. Several methods based on formal statistical techniques have been studied to adjust cross sections used in fast reactor design calculations; nevertheless, these techniques have never been used for epithermal and thermal energy ranges. In this study, the statistical adjustment technique is reviewed, the integral experiments that serve as the adjustment database are presented, and suggested adjustments are discussed. If the cross sections of the main heavy nuclides seem to be well known, this study shows a very strong modification of the 235U capture cross section in the resonance range (∼10%). This trend can be explained by an underestimation of the mean capture width used in the 235U evaluation. The statistical technique used in this study allows us to qualify the JEF2 cross sections with a high quality of confidence.