25 Years of TL Dosimetry at the Institute of Nuclear Physics, Krak w

Niewiadomski, T.

doi:10.1093/oxfordjournals.rpd.a031596

Cited by 26 publications

(10 citation statements)

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“…Each detector was given a number, which determined its fixed localization in a given section of a phantom during each scanning. An automatic RADOS 2000 reader was used to extract the readings (calibration and data extraction was performed by a certified IFJ laboratory in Cracow) [ 4 ].…”

Section: Methodsmentioning

confidence: 99%

Distribution of the radiation dose in multislice computer tomography of the chest – phantom study

Gorycki

Kamiński²,

Studniarek

et al. 2014

Pol J Radiol

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SummaryBackgroundThe most commonly used form of reporting doses in multislice computed tomography involves a CT dose index per slice and dose-length product for the whole series. The purpose of this study was to analyze the actual dose distribution in routine chest CT examination protocols using an antropomorphic phantom.Material/MethodsWe included in the analysis readings from a phantom filled with thermoluminescent detectors (Art Phantom Canberra) during routine chest CT examinations (64 MDCT TK LIGHT SPEED GE Medical System) performed using three protocols: low-dose, helical and angio-CT.ResultsMean dose values (mSv) reported from anterior parts of the phantom sections in low-dose/helical/angio-CT protocols were as follows: 3.74; 16.95; 30.17; from central parts: 3.18; 14.15; 26.71; from posterior parts: 3.01; 12.47; 24.98 respectively. Correlation coefficients for mean doses registered in anterior parts of the phantom between low-dose/helical, low-dose/angio-CT and helical/angio-CT protocols were 0.49; 0.63; 0.36; from central parts: 0.73; 0.66; 0.83, while in posterior parts values were as follows: 0.06; 0.21; 0.57.ConclusionsThe greatest doses were recorded in anterior parts of all phantom sections in all protocols in reference to largest doses absorbed in the anterior part of the chest during CT examination. The doses were decreasing from anterior to posterior parts of all sections. In the long axis of the phantom, in all protocols, lower doses were measured in the upper part of the phantom and at the very lowest part.

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Section: Methodsmentioning

confidence: 99%

Distribution of the radiation dose in multislice computer tomography of the chest – phantom study

Gorycki

Kamiński²,

Studniarek

et al. 2014

Pol J Radiol

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“…The difference between the number of registrations with the results obtained by calculation does not exceed 2.1%. The flux of thermal neutrons (Φ) has been determined on the basis of the relationship: (1) where: N -the number of registrations of tritons or α particles, n j -the number of nuclei in the target 6 Li, σ -reaction 6 Li(n, α) 3 T cross section, ω -correction to the particles solid angle of detection, t -time of measurement.…”

Section: Neutron Sourcementioning

confidence: 99%

“…The role of thermoluminescent detectors (TLD) based on lithium fluoride (LiF) in ionizing radiation field dosimetry is recognized and widely used by many dosimetry services in Poland and abroad [1][2][3][4]. Aside from natural lithium (consisting of 92.41% 7 Li and 7.59% 6 Li) the production of thermoluminescent detectors also uses lithium fluoride enriched and depleted in the isotope 6 Li.…”

Section: Introductionmentioning

confidence: 99%

MTS-6 detectors calibration by using <sup>239</sup>Pu-Be neutron source

Wrzesień

Albiniak

Al-Hameed

2017

Med Pr

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Background: Thermoluminescent detectors, type MTS-6, containing isotope 6 Li (lithium) are sensitive in the range of thermal neutron energy; the 239 Pu-Be (plutonium-and-beryllium) source emits neutrons in the energy range from 1 to 11 MeV. These seemingly contradictory elements may be combined by using the paraffin moderator, a determined density of thermal neutrons in the paraffin block and a conversion coefficient neutron flux to kerma, not forgetting the simultaneous registration of the photon radiation inseparable from the companion neutron radiation. The main aim of this work is to present the idea of calibration of thermoluminescent detectors that consist of a 6 Li isotope, by using 239 Pu-Be neutron radiation source. Material and Methods: In this work, MTS-6 and MTS-7 thermoluminescent detectors and a plutonium-and-beryllium ( 239 Pu-Be) neutron source were used. Paraffin wax fills the block, acting as a moderator. The calibration idea was based on the determination of dose equivalent rate based on the average kerma rate calculated taking into account the empirically determined function describing the density of thermal neutron flux in the paraffin block and a conversion coefficient neutron flux to kerma. Results: The calculated value of the thermal neutron flux density was 1817.5 neutrons/cm 2 /s and the average value of kerma rate determined on this basis amounted to 244 μGy/h, and the dose equivalent rate 610 μSv/h. The calculated value allowed for the assessment of the length of time of exposure of the detectors directly in the paraffin block. Conclusions: The calibration coefficient for the used batch of detectors is (6.80±0.42)×10 -7 Sv/impulse. Med Pr 2017;68(6):705-710

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“…The fingertip LiF TLDs are thin active layer ultrasensitive MCP-Ns (LiF: Mg, Cu, P) dosimeters manufactured by TLD Poland (Kraków, Poland) [11,12]. They are designed as a pellet to measure the personal equivalent dose to the skin, Hp(0.07), defined at the depth of 7 mg/cm 2 , in fields of weakly penetrating radiation [13] (soft X-rays and b radiation).…”

Section: Beta-dosimeters For Personal Dose Measurementsmentioning

confidence: 99%

“…They are designed as a pellet to measure the personal equivalent dose to the skin, Hp(0.07), defined at the depth of 7 mg/cm 2 , in fields of weakly penetrating radiation [13] (soft X-rays and b radiation). These detectors show flat energy response for X-rays and b-rays, high sensitivity to allow reliable measurement of doses in the microsievert range and good angular characteristics [12]. The sensitive effective layer (8.5 mg/cm 2 with a diameter of 4.5 mm) is bonded with a thick base of undoped LiF [14].…”

Section: Beta-dosimeters For Personal Dose Measurementsmentioning

confidence: 99%