Establishment of neutron dose calibration fields based on a ²⁵²Cf source by Monte-Carlo method
Main Article Content
Abstract
This paper presents calculation results based on Monte-Carlo method to select an appropriate neutron moderator and design four configurations for a 252Cf irradiation system. These configurations provide six neutron spectra with the various average energies (1.04 MeV, 1.38 MeV, 1.69 MeV, 2.05 MeV, 2.46 MeV and 2.93 MeV) suitable for the calibration of neutron survey meters and personal dosimeters.
Article Details
Keywords
²⁵²Cf irradiation system, Monte-Carlo method, neutron moderator, neutron spectrum, neutron dose calibration
References
[2]. IAEA, “Compendium of Neutron Spectra and detector responses for radiation protection purposes”, No. 403, Vienna, 2001.
[3]. ICRP, “Conversion Coefficients for use in Radiological External Radiation”, ICRP Publication 74, Pergamon, 1997.
[4]. ISO 8529-3, “Reference neutron radiations - Part 3: Calibration of area and personal dosimeters and the determination of their response as a function of neutron energy and angle of incidence”, 1995.
[5]. J. G. Young, “Report on a Visit to the Neutron Metrology Laboratories at PTB, NPL and NRPB”, ARL/TR118, ISSN 0157-1400, 1995.
[6]. K.S.Lim, B.H.Kim, S.Y.Chang, “Calibration of Neutron Measuring Instruments by Cf-252 Neutron Source”, Transactions of the Korean Nuclear Society Autumn Meeting, Busan, Korea, October 27-28, 2005.
[7]. Hoang Van Nguyen, Pham Quang Dien, “Research on manufacturing an Albedo Neutron Dosimeter”, KC-09-16, Hanoi, 1995.
[8]. Hoang Van Nguyen et al., “Research in establishing a neutron dose calibration system based on an Am-241/Be source”, Sci. Theme CS/06/01-12, Dalat, 2006.
[9]. Oak Ridge National Laboratory, MCNP — A General Monte Carlo N-Particle Transport Code, Version 5, 2004.