Comparison of the response and behavior of TL neutron - gamma dosimeters used in individual dosimetry system for 241Am-Be and 252Cf sources

Authors

10.22052/2.1.27

Abstract

Neutron individual dosimetry is challenging subject in dosimetry field. Thermoluminescent dosimeter (TLD) is one of the types of personal dosimeters that is extremely used to determine the doses of neutron sources. Typically, this type of dosimeter is used in different centers with a variety of applications after calibration with a standard neutron radiation sources. Usually, materials of TL crystal that used in personal dosimetry purposes have the effective atomic number of soft tissue such as (LiF). But, importantly, the heavy dependence of the neutron spectrum to geometry of the source location makes the estimation of doses particularly the dose equivalent very difficult. This research is studied on TLD600-700 HARSHAW that used in individual neutron - gamma dosimetry services in Iran. This dosimeters are irradiated with standard sources 241Am-Be and 252Cf at low doses to high doses and their behavior are studied and analyzed. Also the important information about relative response of these dosimeters that irradiated by 241Am-Be and 252Cf sources is presented.

Keywords

References

[1] F. Manouchehri,, F. Torkzadeh, N. Mirzajani, Sh. Jalilian. Thermal Neutron Fluence Measurements Using Thermoluminescence Dosimeter TLD-600. J. Nuclear Sci. and Tech. No. 42, (2008) 1-6. [2] R. Mendez, M.P. Iniguez, R. Barquero, A. Mananeset and et.al. Response Componets of LiF: Mg, Ti Around A Moderated Am-Be Neutron Source. Radiat. Prot. Dosim. Vol 98, No. 2. (2002) 173-178. [3] M. Hajek, Applied Neutron Spectrometry, PhD Thesis,Austria; 2002. [4] R.J. Tanner, D.J. Thomas, D.T. Bartllet, L.G. Hager, N. Horwood, G.C. Taylor. Effect of the Energy Dependence of Response of Neutron Personal Dosemeters Routinely Used in the UK on Accuracy of Dose Estimation, NRPB – W25;(2002). [5] E.B.Souto and L.L Campos, Brazilian Gamma- Neutron Dosimeter: Response to 241Am-Be and 252Cf Neutron Sources, Radiat. Prot. Dosim. (2003) 1 -3. [6] R.V. Griffith, D.E. Hankins, R.B. Gammage, et.al., Recent developments in personal neutron dosimeter, Health Phys. 36 ( 1977), 235 . [7] V.I. Karpova et al., Collected Papers on Several Problems in the Dosimetry and Radiometry of Ionizing Radiation [inRussian],Yu.V. Sivintsev, ed., Atomizdat, No.i, p.98, Moscow (1990). [8] H.B. Greiss, Neutron Spectrum of Am-Be Source, Nucleonik (In German)10 , (1968) 283-287. [9] F. F. Morehead and F. DanielsThermoluminescence and Coloration of Lithium Fluoride Produced by Alpha Particles, Electrons, Gamma Rays, and Neutrons , J. Chem. Phys. 27 (1957) 1318. [10] Y.S. Yoo, P.S. Kim and P.S. Moon. A study on the neutron dosimetry with LiF themoluminescent. J. Korean. Nucl. Soci. Vol. 7, No. 3, (1975) 191-199. [11] N. Goldstein, W. G. Miller and P. F. Rago, Additivity of neutron and gamma exposures for TLD dosimeters. Health Phys. 18(1970) 157-158.

Files

Share

How to cite

Statistics