Neutronics and nuclear data: achievements in computational simulations and experiments in support of fusion reactor design

被引:12
作者
Fischer, U
Batistoni, P
Ikeda, Y
Youssef, MZ
机构
[1] Forschungszentrum Karlsruhe, Inst Kern & Energietech, D-76021 Karlsruhe, Germany
[2] ENEA, Fus Div, I-00044 Frascati, Italy
[3] JAERI, Spallat Neutron Lab, Tokai, Ibaraki 3191195, Japan
[4] Univ Calif Los Angeles, Los Angeles, CA 90095 USA
关键词
fusion; neutronics; nuclear data; integral experiments; data testing;
D O I
10.1016/S0920-3796(00)00236-2
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
An overview is given of the achievements in the field of neutronics and nuclear data for fusion reactor applications. Much progress has been achieved in this area over the past decade, largely as result of the effort spent by the national fusion technology programmes in the EU, Japan, the RF and the US and supported by the international thermonuclear experimental reactor (ITER) project. In conjunction with the conduction of various integral benchmark experiments, this has led to the development of a well-qualified nuclear database for fusion applications, the international fusion evaluated nuclear data library (FENDL), and the assessment of safety margins derived for reactor design relevant responses. Further development work is required to enable direct uncertainty calculations for fusion reactor applications. This requires a Monte Carlo code capable for full sensitivity and uncertainty calculations along with high-quality, co-variance data as well as suitable integral benchmark experiments for qualification and validation purposes. This proceeding will allow specifying, by Monte Carlo calculations, the design relevant responses with their associated uncertainties and thus directly providing the related design safety margins. (C) 2000 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:663 / 680
页数:18
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