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
相关论文
共 50 条
  • [31] How to Produce a Reactor Neutron Spectrum Using a Proton Accelerator
    Burns, K.
    Wootan, D.
    Gates, R.
    Schmitt, B.
    Asner, D. M.
    23rd International Conference on the Application of Accelerators in Research and Industry - CAARI 2014, 2015, 66 : 471 - 480
  • [32] Prompt neutron lifetime calculations for the NIRR-1 reactor
    Ibrahim, Yakubu V.
    Adeleye, Micheal O.
    Njinga, Raymond L.
    Odoi, Henry C.
    Jonah, Sunday A.
    ADVANCES IN ENERGY RESEARCH, 2015, 3 (02): : 125 - 131
  • [33] Neutron energy spectra calculations in the low power research reactor
    Omar, H.
    Khattab, K.
    Ghazi, N.
    INDIAN JOURNAL OF PURE & APPLIED PHYSICS, 2011, 49 (11) : 723 - 730
  • [34] Feasibility study on a simple method of retrospective neutron dosimetry for reactor internals and reactor vessel
    Hayashi, Katsumi
    Tayanma, Ryuuichi
    Watanabe, Yoshio
    Nakamura, Tomomi
    Kubota, Isamu
    Hayashi, Haruhisa
    Yamasaki, Tadashi
    Yuya, Hideki
    REACTOR DOSIMETRY: 12TH INTERNATIONAL SYMPOSIUM, 2008, 1490 : 3 - 10
  • [35] Testing of various neutron filters in reference neutron field in LR-0 reactor for nuclear data validation and verification
    Kostal, Michal
    Losa, Evzen
    Schulc, Martin
    Czakoj, Tomas
    Peltan, Tomas
    Simon, Jan
    Juricek, Vlastimil
    Rypar, Vojtech
    Thiollay, Nicolas
    Destouches, Christophe
    Radulovic, Vladimir
    Trkov, Andrej
    Capote, Roberto
    APPLIED RADIATION AND ISOTOPES, 2021, 169
  • [36] Thermal neutron irradiation field design for boron neutron capture therapy of human explanted liver
    Bortolussi, S.
    Altieri, S.
    MEDICAL PHYSICS, 2007, 34 (12) : 4700 - 4705
  • [37] Design of a portable directional neutron source finder
    Yamanishi, H
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2005, 544 (03) : 643 - 648
  • [38] Calculations of the thermal and fast neutron fluxes in the Syrian miniature neutron source reactor using the MCNP-4C code
    Khattab, K.
    Sulieman, I.
    APPLIED RADIATION AND ISOTOPES, 2009, 67 (04) : 535 - 538
  • [39] Measurement, simulation and uncertainty quantification of the neutron flux at the McMaster Nuclear Reactor
    MacConnachie, Elizabeth L.
    Novog, David R.
    ANNALS OF NUCLEAR ENERGY, 2021, 151
  • [40] Monte Carlo simulation of the Greek research reactor neutron irradiation facilities
    Stamatelatos, I. E.
    Varvayanni, M.
    Tzika, F.
    Ale, A. B. F.
    Catsaros, N.
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 2007, 263 (01) : 136 - 139
12345