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Fusion Science and Technology
Latest News
In transition: Commercializing fusion power
Commercial fusion power is closer than ever. There are now around 30 U.S. fusion companies, several of which claim to be on track to connect to the grid as early as the 2030s.
Tokamak and laser inertial confinement approaches benefit from decades of research at facilities such as the National Ignition Facility (NIF) at Lawrence Livermore National Laboratory and ITER, with alternative concepts including stellarator, magnetic mirror, and Z-pinch confinement also making notable progress as private and government funding for fusion increases.
Anton Lüthi, Rakesh Chawla, Gérald Rimpault
Nuclear Science and Engineering | Volume 138 | Number 3 | July 2001 | Pages 233-255
Technical Paper | doi.org/10.13182/NSE01-A2211
Articles are hosted by Taylor and Francis Online.
A new calculational scheme has been developed for the accurate assessment of gamma heating in fast reactors, its special feature being the determination of the gamma source distribution that is formulated in a near-to-exact manner. The improved methodology, which has been implemented into the ERANOS (European Reactor Analysis Optimized System) code package, is currently validated for Pu-burning configurations, for which gamma-heating target accuracies are particularly high. This has been accomplished through comparisons with new integral measurements conducted at the MASURCA facility, as well as with reevaluated earlier experiments. In the new measurements, absolute gamma-heating rates were determined in PuO2/UO2-fueled cores surrounded by a steel/sodium reflector, mainly using TLD-700 thermoluminescent dosimeters. Thereby, a considerable effort was undertaken to minimize systematic errors. The calculation/experiment values determined from the analysis of the critical experiments are 0.90 for the PuO2/UO2 core region, 0.84 for the steel/sodium reflector, and 0.89 for an internal steel/sodium diluent zone. The most plausible causes for the observed discrepancies have been identified to be data related, i.e., too low fission gamma energies and too low capture cross sections for the structural elements. The transferability of the current validation findings to a modified Superphénix configuration, in which the radial fertile blanket is replaced by a steel/sodium reflector, and to the 1500 MW(electric) Pu-burning CAPRA 4/94 reference design has been demonstrated.