DocumentCode :
433834
Title :
Initial results of neutronics experiments for evaluation of tritium production rate in solid breeding blanket
Author :
Nishitani, T. ; Ochiai, K. ; Klix, A. ; Verzilov, Y. ; Sato, S. ; Yamauchi, M. ; Nakao, M. ; Hori, J. ; Enoeda, M.
Author_Institution :
Japan Atomic Energy Res. Inst., Ibaraki, Japan
fYear :
2003
fDate :
14-17 Oct. 2003
Firstpage :
454
Lastpage :
457
Abstract :
In order to examine the accuracy of the tritium production rate (TPR) calculations, neutronics experiments have been performed with D-T neutrons at Fusion Neutronics Source (FNS) of JAERI by using a mockup of the solid breeder blanket consisting of F82H blocks, Li2TiO3 blocks with a 6Li enrichment of 40 and 95 %, and beryllium blocks. Pellet detectors made of Li2CO3 and Li2TiO3 enriched to the proper 6Li volume concentration were embedded in stacks in a hole of each Li2TiO3 layer. After D-T neutron irradiation, the amount of tritium produced in the pellets was measured by liquid scintillation counting methods, of which accuracy was 10%. The TPR was calculated by the Monte Carlo codes MCNP-4B with the nuclear data libraries JENDL-3.2, JENDL-FF, ENDF-VI and FENDL-2. The C/E values of the TPR were 1.15 on average. To clarify the accuracy of the macroscopic absorption cross section for beryllium blocks, the low energy neutron transport was investigated by pulsed D-T neutron injection into the beryllium assembly. The macroscopic absorption cross section of beryllium blocks was about 40 % larger than that of pure beryllium. However, it is found that such amount of impurities does not affect TPR significantly.
Keywords :
Monte Carlo methods; fusion reactor blankets; liquid scintillation detectors; neutron effects; neutron transport theory; nuclear engineering computing; plasma beam injection heating; 6Li enrichment; 6Li volume concentration; C/E values; D-T neutron irradiation; D-T neutrons; ENDF-VI; F82H blocks; FENDL-2; Fusion Neutronics Source; JENDL-3.2; JENDL-FF; Li2CO3; Li2TiO3 blocks; MCNP-4B; Monte Carlo codes; beryllium assembly; beryllium blocks; liquid scintillation counting methods; low energy neutron transport; macroscopic absorption cross section; neutronics experiments; nuclear data libraries; pellet detectors; pulsed D-T neutron injection; solid breeding blanket; tritium production rate; Absorption; Building materials; Coolants; Detectors; Impurities; Inductors; Neutrons; Production; Solids; Steel;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on
Print_ISBN :
0-7803-7908-X
Type :
conf
DOI :
10.1109/FUSION.2003.1426681
Filename :
1426681
Link To Document :
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