Development of a neutron detector for radiation protection monitoring
Main Article Content
Abstract
The paper presents the results of the development of a neutron detector for radiation protection purposes. Monte Carlo simulations, using MCNP5 code, were performed to optimize the configuration of the neutron detector. The developed detector consists of a 3He proportional counter embedded in a multi-layer moderator made of high-density polyethylene (HDPE) and Cadmium. The characteristics of the developed neutron detector including neutron fluence response and ambient dose equivalent response were calculated, analyzed and compared with those from other neutron survey meters. The simulation model and computed results were assessed through experimental measurements at the Secondary Standards Dosimetry Laboratory of the Institute for Nuclear Science and Technology (INST). A good agreement between the simulated and experimental results was observed within 9.3% for 241Am-Be source and four simulated workplace neutron fields.
Article Details
Keywords
developed neutron detector, neutron fluence response, ambient dose equivalent response
References
[2]. Isheeta Seth, L. Jeffrey et al., “Neutron Exposures in Human Cells: Bystander Effect and Relative Biological Effectiveness”, PloS One, 2014.
[3]. ICRP, “The International Commission on Radiological Protection”, Publication 74, 1996.
[4]. T.M. Oakes, S.L. Bellinger et al., “An accurate and portable solid state neutron rem meter”, Nuclear Instruments and Methods in Physics Research A, Vol 719, 6–12, 2013.
[5]. J. Saegusa et al., “Evaluation of energy responses for neutron dose-equivalent meters made in Japan”, Nucl. Ins. and Meth. in Phys. Res. A, Vol 516, 193–202, 2004.
[6]. Burgkhardt, G. Fieg, Klett, A. et al., “The neutron fluence and H*(10) response of the new LB 6411 rem counter”, Radiation Protection Dosimetry, Vol. 70(1-4), 361-364, 1997.
[7]. C. Birattari, A. Esposito, A. Ferrari, et al., “Calibration of the neutron rem counter LINUS in the energy range from thermal to 19 MeV”, Nucl Instruments and Methods in Physics, Vol. 324, 232-238, 1993.
[8]. Richard H. Olsher, Hsiao-Hua Hsu, et al., “WENDI: An improved neutron rem meter”, Health Physics 79(2), 170-181, 2000.
[9]. M. Caresana, C. Cassell, M. Ferrarini, et al., “A new version of the LUPIN detector: Improvements and latest experimental verification”, Review of Scientific Instruments, 116-124, 2014.
[10]. H. Richard, T. David, et al., “PRESCILA: a new, lightweight neutron rem meter”, Health Phys, Vol 86, 603-612, 2004.
[11]. Briesmeister, “MCNP:A General Monte Carlo N-Particle Transport Code Version5”, Los Alamos, Manual, 1977.
[12]. Roberto Bedogni, “Neutron spectrometry with Bonner Spheres for area monitoring in particle accelerators”, Radiation Protection Dosimetry, Vol 146, 383-394, 2011.
[13]. P.F. Rose, “ENDF-201, ENDF/B-VI Summary Documentation”, BNL-NCS-17541, fourth ed., 1991.
[14]. Thomas E.Booth, “A sample problem for variance reduction in MCNP”, LA-10363-MS, 1985.
[15]. IEC international standard, “Radiation protection instrumentation – Neutron ambient dose equivalent (rate) meters”, IEC-61005, 2014.
[16]. Thiem Ngoc Le et al., “Simulated workplace neutron fields of 241Am–Be source moderated by polyethylene spheres”, Journal of Rad. and Nucl. Chem, Vol 321, 313–321, 2019.
[17]. Le Ngoc Thiem et al., “Characteristics of Simulated Workplace Neutron Standard Fields”, Communications in Physics, Vol. 30, 71-78, 2020.