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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.
C. Vaglio-Gaudard, O. Leray, A. C. Colombier, O. Gueton, J. P. Hudelot, M. Valentini, J. Di Salvo, A. Gruel, J. C. Klein, A. Roche, D. Beretz, B. Geslot, J. M. Girard, C. Jammes, P. Sireta
Nuclear Science and Engineering | Volume 175 | Number 3 | November 2013 | Pages 318-328
Technical Paper | doi.org/10.13182/NSE12-67
Articles are hosted by Taylor and Francis Online.
A new experimental program, named AMMON, was performed between late 2010 and early 2013 in the EOLE zero-power experimental reactor at CEA Cadarache. It is dedicated to the analysis of the neutron and photon physics of the Jules Horowitz Reactor (JHR), the next international materials testing reactor under construction in France. The objective of the program is to provide measurement data for the experimental validation of the calculation tools developed for the JHR design and safety studies. The first core configuration, the so-called reference configuration, was loaded in 2012; it consisted of an experimental zone of seven JHR assemblies with U3Si2-Al, 27% 235U enriched fuel curved plates surrounded by a driver zone with 622 standard pressurized water reactor uranium oxide fuel pins. It has been instrumented and studied throughout the first year of the experimental program.The final analysis of the AMMON/REF neutron measurements is presented in this paper. It is based on calculations performed with the three-dimensional reference Monte Carlo TRIPOLI-4.7 code and the JEFF3.1.1 European library. The comparison between calculation and experiment makes it possible to calibrate the bias due to nuclear data on the calculated neutron parameters. It highlights good agreement between calculation and experiment concerning reactivity, power distribution in the experimental zone, fuel plate conversion ratios, and core kinetics parameters. The reactivity prediction is very satisfactory, despite the presence of a large aluminum quantity in the core: calculation-to-experiment comparison (C - E) = + 365 ± 334 pcm (1). For the other neutron parameters (assembly power distribution, plate conversion ratios, and kinetics parameters), the (C - E)/E discrepancies are within the experimental uncertainty (2).