Calculated neutron sensitivities of CaF2 and 7LiF thermoluminescent dosimeters

Rinard, P.M.; Simons, G.G.

doi:10.1016/s0029-554x(79)95780-x

Cited by 18 publications

(3 citation statements)

References 8 publications

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“…Various authors (Furuta and Tanaka 1972, Alsmiller and Barish 1974, Spurny et a1 1976a, Tanaka and Furuta 1977 have assumed that the neutron sensitivity is closely related to the kerma. Some calculations (Prokic 1971, Tanaka and Furuta 1977, Rinard and Simons 1979 have attempted to take into account varying relative efficiencies of different ions to induce TL by assuming a universal TL-LET (linear energy transfer) curve. This approach should be regarded as a very crude approximation for the following reasons:…”

Section: 42mentioning

confidence: 99%

“…At 15 MeV, for 6LiF, the Patrick et a1 (1975) and Jahnert (1972) data yield -5 6oCo R per 10" n cm2 and the Tochilin data -10 6oCo R per 10" n cm-2 whereas for 7LiF the respective sensitivities are -3 and -8 6oCo R per 10" n cm-2 respectively. Rinard and Simons (1979) calculated 4 6oCo R per 10" n cm-2 for 7LiF and Tanaka and Furuta (1977) measured 10 6oCo R per lo1' n cmp2 for both 6LiF and LiF. Attix et a1 (1973) has also commented on the dangers of selecting published values of fast-neutron sensitivities; measurement of the y-ray component of the NRL fast-neutron beam with CaF2:Mn and 'LiF TLDS yielded negative values for the gamma dose using published fast-neutron sensitivities.…”

Section: 42mentioning

confidence: 99%

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The theoretical and microdosimetric basis of thermoluminescence and applications to dosimetry

Horowitz

1981

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155

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TLproperties of many materials and their interaction with various types of radiation fields.+ The thermoluminescent efficiency, ak, is the ratio of the mean energy emitted as TL light, E+, to the mean energy, E, imparted to the TL material by the radiation field, a k = E+/B. d is sometimes referred to as the 'integral' dose in the irradiated volume and is defined as the expectation value of the imparted energy. $ The relative TL response, q k , , of a TL material of mass m, and volume V, is the ratio of the TL efficiences for the two radiation fields, k, I at 'low dose' Do, i.e. where .E+ is increasing linearly with dose:ak(Do)/ar(Do). 9: A tissue-equivalent material is one with atomic composition which closely approximates to the atomic composition of tissue. TL materials such as LiF, Li2B407, Be0 are nonetheless referred to as approximately 'tissue-equivalent' materials in gamma radiation fields because their effective atomic number and mass energy absorption coefficients for photoelectric absorption approximate to those of tissue (e.g. Jayachandran 1971).Y S Horo w itz irradiated material. Johnson also describes the use of an integrating period in the readout cycle which approximately cancels the growth of peaks 4-5 due to storage by including a certain fraction of peaks 2-3 which exhibit stronger fading. Ehrlich (1974) using fast preheating to 160°C did not observe 'sensitivity-transfer' in TLD-700; however, fading increased to 15% after 4 days. Indeed the fading of 'unannealed' LiF-TLDS is strongly dependent on the preheat cycle (Webb and Phykitt 1971, De Planque et a1 1980). Mason et a1 (1976) studied the effect of Ti in TLD-700 ( T1 = 300 "C, tl = 30 min) on the relative trap distributions associated with peaks 2 and 5 and concluded that the results of Booth etal (1972) were inconsistent with their data.'7. '7.' 7.

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Section: 42mentioning

confidence: 99%

Section: 42mentioning

confidence: 99%

The theoretical and microdosimetric basis of thermoluminescence and applications to dosimetry

Horowitz

1981

pmb

155

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“…Thus, an energy-dependent effective neutron kerma in the TLD material was added as an external response for the MCNP calculation. The energydependent effective neutron kerma for CaF 2 :Mn was a composite of the response from Henninger response [He82] at high energies and Rinard response [Ri79] at low energies. The transition between the two functions begins at 1.3125E+04 eV and concludes at 1.0750E+03 eV.…”

Section: Direct Neutron Kermamentioning

confidence: 99%

Neutron Contribution to CaF2:Mn Thermoluminescent Dosimeter Response in Mixed (n/y) Field Environments

DePriest¹

2002

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Thermoluminescent dosimeters (TLDs), particularly CaF 2 :Mn, are often used as photon dosimeters in mixed (n/γ) field environments. In these mixed field environments, it is desirable to separate the photon response of a dosimeter from the neutron response. For passive dosimeters that measure an integral response, such as TLDs, the separation of the two components must be performed by post-experiment analysis because the TLD reading system cannot distinguish between photon and neutron produced response. Using a model of an aluminum-equilibrated TLD-400 chip, a systematic effort has been made to analytically determine the various components that contribute to the neutron response of a TLD reading. The calculations were performed for five measured reactor neutron spectra and one theoretical thermal neutron spectrum. The five measured reactor spectra all have dosimetry quality experimental values for aluminum-equilibrated TLD-400 chips. Calculations were used to determined the percentage of the total TLD response produced by neutron interactions in the TLD and aluminum equilibrator. These calculations will aid the Sandia National LaboratoriesRadiation Metrology Laboratory (SNL-RML) in the interpretation of the uncertainty for TLD dosimetry measurements in the mixed field environments produced by SNL reactor facilities.4

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Progress in Neutron Dosimetry for Biomedical Applications

Broerse

Mijnheer

1982

Progress in Medical Radiation Physics

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Calculated neutron sensitivities of CaF2 and 7LiF thermoluminescent dosimeters

Cited by 18 publications

References 8 publications

The theoretical and microdosimetric basis of thermoluminescence and applications to dosimetry

The theoretical and microdosimetric basis of thermoluminescence and applications to dosimetry

Neutron Contribution to CaF2:Mn Thermoluminescent Dosimeter Response in Mixed (n/y) Field Environments

Progress in Neutron Dosimetry for Biomedical Applications

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