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http://dx.doi.org/10.1016/j.net.2016.07.011

Neutron Calibration Field of a Bare 252Cf Source in Vietnam  

Le, Thiem Ngoc (Institute for Nuclear Science and Technology)
Tran, Hoai-Nam (Institute of Research and Development, Duy Tan University)
Nguyen, Khai Tuan (Institute for Nuclear Science and Technology)
Trinh, Giap Van (Institute for Nuclear Science and Technology)
Publication Information
Nuclear Engineering and Technology / v.49, no.1, 2017 , pp. 277-284 More about this Journal
Abstract
This paper presents the establishment and characterization of a neutron calibration field using a bare $^{252}Cf$ source of low neutron source strength in Vietnam. The characterization of the field in terms of neutron flux spectra and neutron ambient dose equivalent rates were performed by Monte Carlo simulations using the MCNP5 code. The anisotropy effect of the source was also investigated. The neutron ambient dose equivalent rates at three reference distances of 75, 125, and 150 cm from the source were calculated and compared with the measurements using the Aloka TPS-451C neutron survey meters. The discrepancy between the calculated and measured values is found to be about 10%. To separate the scattered and the direct components from the total neutron flux spectra, an in-house shadow cone of 10% borated polyethylene was used. The shielding efficiency of the shadow cone was estimated using the MCNP5 code. The results confirmed that the shielding efficiency of the shadow cone is acceptable.
Keywords
$^{252}Cf$ Neutron Source; Neutron Calibration Field; Neutron Flux Spectra; Shadow Cone;
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  • Reference
1 The IAEA/WHO SSDL Network. http://www-naweb.iaea.org/nahu/dmrp/SSDL/login.asp, (accessed on 15.04.16).
2 X-5 Monte Carlo Team, MCNP-A General Monte Carlo Nparticle Transport Code, Version 5, vol. I: Overview and Theory, Los Alamos National Laboratory, California, 2003, p. 334.
3 ICRP Publication 74, Conversion coefficients for use in radiological protection against external Radiation, Ann. ICRP 26 (1996) 3-4.
4 J. McConn Jr., C.J. Gesh, R.T. Pagh, R.A. Rucker, R.G. Williams III, Compendium of Material Composition Data for Radiation Transport Modeling, PNNL-15870 Rev. 1, Pacific North West National Laboratory, Washington, 2011, p. 375.
5 P.F. Rose, ENDF-201, ENDF/B-VI Summary Documentation. BNL-NCS-17541, fourth ed., 1991.
6 ISO 8529-1:2001 (E), Reference Neutron Radiations - Part 1: Characteristics and Methods of Production, ISO, Switzerland, 2001, p. 32.
7 X-5 Monte Carlo Team, MCNP-A General Monte Carlo Nparticle Transport Code, Version 5, vol. II: User's Guide, Los Alamos National Laboratory, California, 2003-Revised 2005, p. 504.
8 ISO 8529-2:2001 (E), Reference Neutron Radiations - Part 2: Calibration Fundamentals of Radiation Protection Devices Related to the Basic Quantities Characterizing the Radiation Field, ISO, Switzerland, 2000, p. 38.
9 H. Park, J.H. Kim, D. Webb, V. Sathian, J.H. Lee, Z. Hui, H. Harano, A. Masuda, T. Matsumoto, N.N. Moisseev, A.V. Didyk, APMP comparison for the calibration of ambient dose equivalent meters in ISO neutron reference fields - APMP.RI(III)-S1, Metrologia 52 (2015). Technology Supplement 06019.
10 IAEA Technical Reports Series, Compendium of Neutron Spectra and Detector Responses for Radiation Protection Purposes - Supplement to Technical Reports Series No. 318. No. 403, 2001, p. 276.
11 IAEA Safety Standards Series, Assessment of Occupational Exposure Due to External Sources of Radiation. No. RS-G-1.3, 1999, p. 98.
12 Neutron Survey Meter TPS-451C. http://www.hitachi.com/businesses/healthcare/products-support/radiation/surveymeter/tps451c/index.html, (accessed on 15.04.16).