Indexed by:Journal Article

Date of Publication:2011-10-01

Journal:14th International Conference on Fusion Reactor Materials (ICFRM)

Included Journals:Scopus、CPCI-S、EI、SCIE

Volume:417

Issue:1-3

Page Number:1341-1344

ISSN:0022-3115

Abstract: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.