Neutron beam design for neutron radiography at the Musashi reactor

被引：7
|
作者：
Matsumoto, T
机构：
[1] Atomic Energy Research Laboratory, Musashi Institute of Technology, Kawasaki-shi 215, Ozenji 971, Asao-ku
来源：
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT | 1996年 / 377卷 / 01期
关键词：
TRIGA reactor; beam design; neutron filter; MCNP;
D O I：
10.1016/0168-9002(96)00115-5
中图分类号：
TH7 [仪器、仪表];
学科分类号：
0804 ; 080401 ; 081102 ;
摘要：
Studies were carried out For the design of a thermal, an epithermal, and a fast neutron beam for neutron radiography (NRG) in the horizontal beam port or in the thermalizing column at the Musashi reactor (TRIGA-II, 100 kW). Thermal, epithermal and fast neutron energy ranges were selected as <0.4 eV, 0.4 eV-10 keV, and >10 keV, respectively. To produce a good neutron beam in terms of intensity and qualify, several materials (bismuth (Bi), silicon (Si) and alumina (Al2O3)) were examined as neutron filters. The MCNP (Monte Carlo Neutron Photon) computations showed that a thermal, an epithermal, and a fast neutron beam could be produced using single-crystal Si, Al2O3 and Bi fillers, respectively. Such neutron beams, if built into the Musashi reactor, could increase extensive application of NRG in Japan.
引用
收藏
页码：48 / 51
页数：4
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