Validation and improvement of Fe, Cr, Ni nuclear data based on bulk shield benchmark experiments
- CEA Cadarache, Saint Paul lez Durance (France)
The inboard shield for protecting the toroidal superconductive magnet is an especially crucial item in the NET/ITER shield design. Although an appreciable amount of nuclear data uncertainties and experimental work analysis has been done in the past, it still has some insufficiency from the point of view of the ITER experts, to support the subsequent EDA Engineering Design phase of the next International Thermonuclear Reactor ITER. With respect to accuracy, the main problem area for ITER neutronics, is the radiation load to the coils. In order to calibrate the actual discrepancy in the calculation of damage and nuclear heating to the TF coil, the authors have analyzed the overall international bulk shield benchmarks. Iron and stainless steel experiments were selected to validate structural material cross-sections, in the European JEF/EFF library.
- OSTI ID:
- 197052
- Report Number(s):
- CONF-940664-; TRN: 95:005767-0229
- Resource Relation:
- Conference: ISFNT-3: international symposium on fusion nuclear technology, Los Angeles, CA (United States), 27 Jun - 1 Jul 1994; Other Information: PBD: 1994; Related Information: Is Part Of Third international symposium on fusion nuclear technology; PB: 362 p.
- Country of Publication:
- United States
- Language:
- English
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