Simulation of Collimator for Neutron Imaging Facility of TRIGA MARK II PUSPATI Reactor

被引:3
|
作者
Zin, Muhammad Rawi Mohamed [1 ]
Jamro, Rafhayudi [2 ]
Yazid, Khairiah [3 ]
Hussain, Hishamuddin [2 ]
Yazid, Hafizal [2 ]
Ahmad, Megat Harun Al Rashid Megat [2 ]
Azman, Azraf [4 ]
Mohamad, Glam Hadzir Patai [3 ]
Hamzah, Nai'im Syaugi [1 ]
Abu, Mohamad Puad [1 ]
机构
[1] Agensi Nuklear Malaysia, Reactor Technol Div, Nucl Phys & Reactor Sect, Kajang 43000, Malaysia
[2] Agensi Nuklear Malaysia, Ind Technol Div, Mat Technol Grp, Kajang 43000, Malaysia
[3] Agensi Nuklear Malaysia, Tech Serv Div, Instrumentat Ctr, Kajang 43000, Malaysia
[4] Agensi Nuklear Malaysia, Tech Serv Div, Prototype Dev Ctr, Kajang 43000, Malaysia
关键词
Neutron; Radiography; PUSPATI;
D O I
10.1016/j.phpro.2015.07.020
中图分类号
O59 [应用物理学];
学科分类号
摘要
Neutron Radiography facility in TRIGA MARK II PUSPATI reactor is being upgraded to obtain better image resolution as well as reducing exposure time. Collimator and exposure room are the main components have been designed for fabrication. This article focuses on the simulation part that was carried out to obtain the profile of collimated neutron beam by utilizing the neutron transport protocol code in the Monte Carlo N-Particle (MCNP) software. Particular interest is in the selection of materials for inlet section of the collimator. Results from the simulation indicates that a combination of Bismuth and Sapphire, each of which has 5.0 cm length that can significantly filter both the gamma radiation and the fast neutrons. An aperture made of Cadmium with 1.0 cm opening diameter provides thermal neutron flux about 1.8 x 10(8) ncm(-2)s(-1) at the inlet, but reduces to 2.7 x 10(6) ncm(-2)s(-1) at the sample plane. Still the flux obtained is expected to reduces exposure time as well as gaining better image resolution. (C) 2015 Published by Elsevier B.V.
引用
收藏
页码:138 / 142
页数:5
相关论文
共 50 条
  • [31] Neutron flux characterisation of the Pavia TRIGA Mark II research reactor for radiobiological and microdosimetric applications
    Alloni, D.
    Prata, M.
    Salvini, A.
    Ottolenghi, A.
    RADIATION PROTECTION DOSIMETRY, 2015, 166 (1-4) : 261 - 265
  • [32] FLEXIBLE NEUTRON RADIOGRAPHY FACILITY USING A TRIGA REACTOR SOURCE
    WHITTEMORE, WL
    LARSEN, JE
    SHOPTAUGH, JR
    MATERIALS EVALUATION, 1971, 29 (05) : 93 - +
  • [33] Simulation of Consequences of Severe Accidents of the TRIGA Mark II Reactor in Vienna using RODOS simulation tool
    Langegger, Eileen
    26TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2017), 2017,
  • [34] A FLEXIBLE NEUTRON RADIOGRAPHY FACILITY USING A TRIGA REACTOR SOURCE
    WHITTEMO.WL
    SHOPTAUG.JR
    LARSEN, JE
    MATERIALS EVALUATION, 1970, 28 (09) : A27 - &
  • [35] Monte Carlo design for a new neutron collimator at the ENEA Casaccia TRIGA reactor
    Burgio, N
    Rosa, R
    APPLIED RADIATION AND ISOTOPES, 2004, 61 (04) : 663 - 666
  • [36] Neutron collimator for neutron radiography applications at tangential port of the TRIGA RC-1 reactor
    Rosa, R.
    Andreoli, F.
    Mattoni, M.
    Palomba, M.
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 2009, 605 (1-2): : 57 - 61
  • [37] Measured neutron flux parameters in the USGS TRIGA MARK I reactor
    Koehl, M. A.
    Rundberg, R. S.
    Braley, J. C.
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2015, 306 (01) : 31 - 38
  • [38] Measured neutron flux parameters in the USGS TRIGA MARK I reactor
    M. A. Koehl
    R. S. Rundberg
    J. C. Braley
    Journal of Radioanalytical and Nuclear Chemistry, 2015, 306 : 31 - 38
  • [39] Simulation on Reactor TRIGA Puspati Core Kinetics Fueled With Thorium (Th) Based Fuel Element
    Mohammed, Abdul Aziz
    Pauzi, Anas Muhamad
    Rahman, Shaik Mohmmed Haikhal Abdul
    Zin, Muhamad Rawi Muhammad
    Jamro, Rafhayudi
    Idris, Faridah Mohamad
    INTERNATIONAL NUCLEAR SCIENCE, TECHNOLOGY AND ENGINEERING CONFERENCE 2015 (INUSTEC2015), 2016, 1704
  • [40] Neutronics analysis of the initial core of the TRIGA Mark II reactor
    Khan, R.
    Stummer, T.
    Boeck, H.
    Villa, M.
    NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (05) : 1463 - 1468