JAPAN ATOMIC-ENERGY RESEARCH-INSTITUTE UNITED-STATES INTEGRAL NEUTRONICS EXPERIMENTS AND ANALYSES FOR TRITIUM BREEDING, NUCLEAR HEATING, AND INDUCED RADIOACTIVITY

被引:9
作者
ABDOU, MA
MAEKAWA, H
OYAMA, Y
YOUSSEF, M
IKEDA, Y
KUMAR, A
KONNO, C
MAEKAWA, F
KOSAKO, K
NAKAMURA, T
BENNETT, E
机构
[1] JAPAN ATOM ENERGY RES INST,INTENSE NEUTRON SOURCE LAB,TOKAI,IBARAKI 31911,JAPAN
[2] JAPAN ATOM ENERGY RES INST,DEPT REACTOR ENGN,FUS NEUTRON LAB,TOKAI,IBARAKI 31911,JAPAN
[3] ARGONNE NATL LAB,FUS POWER PROGRAM,ARGONNE,IL 60439
来源
FUSION TECHNOLOGY | 1995年 / 28卷 / 01期
关键词
INTEGRAL NEUTRONICS EXPERIMENTS; TRITIUM BREEDING; NUCLEAR HEARING;
D O I
10.13182/FST95-A30399
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
A large number of integral experiments for fusion blanket neutronics were performed using deuterium-tritium (D-T) neutrons at the Fusion Neutronics Source facility as part of a 10-yr collaborative program between the Japan Atomic Energy Research Institute and the United States. A series of experiments was conducted using blanket assemblies that contained Li2O, beryllium, steel, and water-coolant channels with a point neutron source in a closed geometry that simulated well the neutron spectra in fusion systems. Another series of experiments was conducted using a novel approach in which the point source simulated a pseudo-line source inside a movable annular blanket test assembly, thus providing a better simulation of the angular flux distribution of the 14-MeV neutrons incident on the first wall of a tokamak system. A number of measurement techniques were developed for tritium production, induced radioactivity, and nuclear heating. Transport calculations were performed using three-dimensional Monte Carlo and two-dimensional discrete ordinates codes and the latest nuclear data libraries in Japan and the United States. Significant differences among measurement techniques and calculation methods were found. To assure a 90% confidence level for tritium breeding calculations not to exceed measurements, designers should use a safety factor > 1.1 to 1.2, depending on the calculation method. Such a safety factor may not be affordable with most candidate blanket designs. Therefore, demonstration of tritium self-sufficiency is recommended as a high priority for testing in near-term fusion facilities such as the International Thermonuclear Experimental Reactor (ITER). The radioactivity measurements were performed for > 20 materials with the focus on gamma emitters with half-lives < 5 yr. The ratio of the calculated-to-experimental (C/E) values ranged between 0.5 and 1.5, but it deviated greatly from unity for some materials with some cases exceeding 5 and others falling below 0.1. Most discrepancies were attributed directly to deficiencies in the activation libraries, particularly errors in cross sections for certain reactions, A microcalorimetric technique was vastly improved, and it allowed measurements of the total nuclear heating with a temperature rise as low as 1 mu K/s. The C/E ratio for nuclear heating deviated from 1 by as much as 70% for some materials but by only a few percent for others.
引用
收藏
页码:5 / 38
页数:34
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