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论文类型：期刊论文

发表时间：2011-10-01

发表刊物：14th International Conference on Fusion Reactor Materials (ICFRM)

收录刊物：SCIE、EI、CPCI-S、Scopus

卷号：417

期号：1-3

页面范围：1341-1344

ISSN号：0022-3115

摘要：A LiD assembly was proposed to produce fusion neutrons from thermal neutrons in D(2)O region of the China Advanced Research Reactor (CARR). The transportation of produced fusion neutrons in the LID assembly can obtain the fusion neutron flux in its central hole. The neutron flux and the distribution of (6)Li(n,alpha) reaction rate in the LiD assembly were calculated by a computer simulation method with MCNP code. The calculation results show that the fusion neutron flux in the central hole of LiD assembly, Phi, is dependent on the size and structure of assembly, (6)Li enrichment, tritium concentration in LiD rods and the physical state of LiD. In the case of LiD rods containing 5% tritium and (6)Li enrichment 20%, Phi value reaches to 5.4 x 10(13) cm(-2) s(-1), when the assembly was placed at the thermal neutron flux about 8.0 x 10(14) cm(-2) s(-1) in CARR. (C) 2011 Elsevier B.V. All rights reserved.