Response optimization of neutron dosimetry in thermal and fast energy range for a diode detector

Authors

10.22052/2.2.1

Abstract

During the last few years, real time gamma and neutron dosimeters have been developed and semiconductor diodes are frequently used in these dosimeters. Semiconductor diodes are used to charged particle detection. For sensitizing the detector to neutrons, a converter layer is contacted on the front surfaces of them. Incident neutrons interact with the converter and produce charged particles that can deposit their energy in the detectors and produce a signal. To cover the energy range of thermal and fast neutrons, a silicon diode detector with thermal neutron converters (6LiF) and fast neutron converter (polyethylene) have been used. Response of the diode detector to neutron radiation is depending on the neutron converter and varying of the neutron converter characteristics is performed for achieving dosimetry in the different energies. To achieve proper dosimetry response in a wide range of energy response 0.01 eV-15 MeV, the optimum thickness of the thermal and fast neutron converter is determined 4 micron and one millimeter respectively. The results show that the dosimetry response in the different neutron energies, to some extent was appropriate, and the deviation is acceptable in the wide range of energy

Keywords


[1] Gad Shani, \"Radiation Dosimetry: instrumentation and methods\", Second Edition, CRC Press, (2000) [2] H. Zaki Dizaji, M. Shahriari and GR. Etaati, \"Monte Carlo Calculation of CR-39 efficiency for fast neutron detection using a combination of MCNP and SRIM codes, and comparison with experimental results\", Radiat. Meas. Vol. 42, 1332-1334, (2007) [4] M. Wielunski, R. Schutz, E. Fantuzzi, A. Pagnamenta, W. Wahl, J. Palfalvi, P. Zombori, A. Andrasi, H. Stadtmann, Ch. Schmitzer, \"Study of the sensitivity of neutron sensors consisting of a converter plus Si charged-particle detector\", Nucl. Instr. and Meth. A, 517 240–253, (2004) [5] Khalid A. Alyousef, \"A Novel Approach to mixed field dosimetry utilizing prototype silicon based P-I-N diodes\", the thesis for the degree of doctor of philosophy, Wayne state university, Detriot, Michigan, (2006) [6] C. Guardiola, C. Fleta, D. Quirion, J. Rodriguez, M. Lozano, F. Teixidor, C. Vinas, A. R. Popescu, C. Domingo, K. Amgarou, \"First investigations of a silicon neutron detector with a carborane converter\", Journal of Instrumentation, Vol. 6, (2011) [7] T. Nunomiya, S. Abe, K. Aoyama, T. Nakamura, \"Development of advanced-type multi-functional electronic personal dosemeter, Radiation Protection Dosimetry\", Vol. 126, 284–287, (2007) [8] Denise B. Pelowitz, \"Monte Carlo N-Particle Transport Code System for Multiparticle and High Energy Applications\", Version 2.6.0, OAK RIDGE NATIONAL LABORATORY, (2008) [9] ICRP 74, Conversion coefficients for use in radiological protection against external radiation. ICRP Publication 74, Ann. ICRP 26 (3/4) (1996). [10] T. Bolognese-Milsztajn, M. Ginjaume, M. Luszik-Bhadra, F. Vanhavere, W. Wahl and A. Weeks, Active personal dosemeters for individual monitoring and other new developments, Radiat. Prot. Dosim. Vol. 112, 141–168 (2004). [11] M. Luszik-Bhadra, A prototype personal neutron dosemeter with one silicon diode, Radiat. Prot. Dosim., Vol. 96, pp. 227–229 (2001). [12] G. Lindstrom, Radiation damage in silicon detectors, 9th European Symposium on Semiconductor Detectors, Schlo Elmau, June 23-27 (2002).