Corrections of HPGe detector efficiency curve due to true coincidence summing by program EFFTRAN and by Monte Carlo simulations

Knežević, Jovana; Mrdja, D.; Hansman, Jan; Bikit, Kristina; Forkapić, Sofija; Bikit, I.; Velimirovic, Danijel; Kuzmanović, Predrag

doi:10.1016/j.apradiso.2022.110421

Cited by 4 publications

(2 citation statements)

References 20 publications

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“…[T-deposit] function was used to evaluate energy deposition inside the HPGe detector and the ε values for each radionuclide. For 88 Y and 60 Co, the ε values considering true coincidence summing (TCS) due to the simultaneous emission of two γ-rays 23 were evaluated using the "iscorr" parameter. After the validation, the ε values of the activation samples used in this study were evaluated in the simulation.…”

Section: A P P E N D I X a : Ac T I Vat I O N M E T H O D A N D T H E...mentioning

confidence: 99%

Out‐of‐field dosimetry using a validated PHITS model and computational phantom in clinical BNCT

Kakino,

Hu,

Tanaka

et al. 2023

Medical Physics

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BackgroundThe out‐of‐field radiation dose for boron neutron capture therapy (BNCT), which results from both neutrons and γ‐rays, has not been extensively evaluated. To safely perform BNCT, the neutron and γ‐ray distributions inside the treatment room and the whole‐body dose should be evaluated during commissioning. Although, certain previous studies have evaluated the whole‐body dose in the clinical research phase, no institution providing BNCT covered by health insurance has yet validated the neutron distribution inside the room and the whole‐body dose.PurposeTo validate the Monte Carlo model of the BNCT irradiation room extended for the whole‐body region and evaluate organ‐at‐risk (OAR) doses using the validated model with a human‐body phantom.MethodsFirst, thermal neutron distribution inside the entire treatment room was measured by placing Au samples on the walls of the treatment room. Second, neutron and gamma‐ray dose‐rate distributions inside a human‐body water phantom were measured. Both lying and sitting positions were considered. Bare Au, Au covered by Cd (Au+Cd), In, Al, and thermoluminescent dosimeters were arranged at 11 points corresponding to locations of the OARs inside the phantom. After the irradiation, γ‐ray peaks emitted from the samples were measured by a high‐purity germanium detector. The measured counts were converted to the reaction rate per unit charge of the sample. These measurements were compared with results of simulations performed with the Particle and Heavy Ion Transport code System (PHITS). A male adult mesh‐type reference computational phantom was used to evaluate OAR doses in the whole‐body region. The relative biological effectiveness (RBE)‐weighted doses and dose‐volume histograms (DVHs) for each OAR were evaluated. The median dose (D50%) and near‐maximum dose (D2%) were evaluated for 14 OARs in a 1‐h‐irradiation process. The evaluated RBE‐weighted doses were converted to equivalent doses in 2 Gy fractions.ResultsExperimental results within 60 cm from the irradiation center agreed with simulation results within the error bars except at ±20, 30 cm, and those over 70 cm corresponded within one digit. The experimental results of reaction rates or γ‐ray dose rate for lying and sitting positions agreed well with the simulation results within the error bars at 8, 4, 11, 7 and 7, 4, 7, 6, 5, 6 out of 11 points, respectively, for Au, Au+Cd, In, Al, and TLD. Among the detectors, the discrepancies in reaction rates between experiment and simulation were most common for Au+Cd, but were observed randomly for measurement points (brain, lung, etc.). The experimental results of γ‐ray dose rates were systematically lower than simulation results at abdomen and waist regions for both positions. Extending the PHITS model to the whole‐body region resulted in higher doses for all OARs, especially 0.13 Gy‐eq increase for D50% of the left salivary gland.ConclusionThe PHITS model for clinical BNCT for the whole‐body region was validated, and the OAR doses were then evaluated. Clinicians and medical physicists should know that the out‐of‐field radiation increases the OAR dose in the whole‐body region.

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Section: A P P E N D I X a : Ac T I Vat I O N M E T H O D A N D T H E...mentioning

confidence: 99%

Out‐of‐field dosimetry using a validated PHITS model and computational phantom in clinical BNCT

Kakino,

Hu,

Tanaka

et al. 2023

Medical Physics

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“…In addition, during the analysis, there is a need for gamma-spectrometric measurements of high-intensity γ-radiation fluxes from high-level nuclear materials. Therefore, there is a need to attenuate the intensity of γ-radiation to reduce miscalculations associated with detector loading (its dead time) and, accordingly, corrections for cascade summation [4].…”

Section: Introductionmentioning

confidence: 99%

EMPIRICAL FORMULA FOR THE DEPENDENCE OF HPGe-DETECTOR EFFICIENCY ON ENERGY AND DISTANCE FOR SHIELDED GAMMA-RAY SOURCES

Pylypchynets¹,

Lengyel²,

Парлаг³

et al. 2023

Problems of Atomic Science and Technology

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The accuracy of gamma-spectrometric measurements in the isotopic analysis of shielded nuclear materials depends on the accuracy of the detector calibration in terms of energy efficiency, which should take into account corrections related to the measurement geometry and the absorption of γ-radiation by the shield material. The results of experimental studies of the energy efficiency of the HPGe-detector measured at fixed distances between the calibration source and the detector (50 and 100 mm) in the presence and absence of an absorbing shield made of stainless steel 12X18H10T (thickness ‒ 9.6 mm) are presented. On the basis of experimental data, an empirical description of the efficiency dependence for fixed distances between the gamma radiation source and the detector in the presence of a stainless steel absorbing shield was obtained.

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Low-level gamma ray counting on environmental samples

Mrdja,

Forkapic,

Hansman

et al. 2024

Journal of Environmental Radioactivity

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Corrections of HPGe detector efficiency curve due to true coincidence summing by program EFFTRAN and by Monte Carlo simulations

Cited by 4 publications

References 20 publications

Out‐of‐field dosimetry using a validated PHITS model and computational phantom in clinical BNCT

Out‐of‐field dosimetry using a validated PHITS model and computational phantom in clinical BNCT

EMPIRICAL FORMULA FOR THE DEPENDENCE OF HPGe-DETECTOR EFFICIENCY ON ENERGY AND DISTANCE FOR SHIELDED GAMMA-RAY SOURCES

Low-level gamma ray counting on environmental samples

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