The effect of different sample-calibrant composition in gamma-ray spectrometry for the assessment of the radiation dose rate in the luminescence dating of sediments

2004 ◽  
Vol 262 (1) ◽  
pp. 261-267 ◽  
Author(s):  
F. De Corte ◽  
D. Vandenberghe ◽  
S. M. Hossain ◽  
A. De Wispelaere ◽  
P. Van den Haute
Keyword(s):  
Radiation Dose ◽  
Dose Rate ◽  
Gamma Ray ◽  
Luminescence Dating ◽  
Gamma Ray Spectrometry ◽  
Radiation Dose Rate

scholarly journals Conceptual Shield Design for Boron Neutron Capture Therapy Facility Using Monte Carlo N-Particle Extended Simulator with Kartini Research Reactor as Neutron Source

2020 ◽  
Vol 35 (3) ◽  
pp. 177-181
Author(s):  
Afifah Hana Tsurayya ◽  
Azzam Zukhrofani Iman ◽  
R. Yosi Aprian Sari ◽  
Arief Fauzi ◽  
Gede Sutresna Wijaya
Keyword(s):  
Monte Carlo ◽  
Radiation Dose ◽  
Dose Rate ◽  
Neutron Source ◽  
Gamma Ray ◽  
Outer Part ◽  
Radiation Shielding ◽  
Radiation Dose Rate ◽  
Boron Neutron Capture ◽  
Radiation Workers

The research aims to measure the radiation dose rate over the radiation shielding which is made of paraffin and aluminium and to determine the best shield material for the safety of radiation workers. The examination used MCNP (Monte Carlo N-Particle) simulator to model the BNCT neutron source and the shield. The shield should reduce radiation to less than the dose limit of 10.42 µSv/h, which is assumed to be the most conservative limit when the duration of workers is 1920 h. The first design resulted in a radiation dose rate which was still greater than the limit. Therefore, optimization was done by adding the lead on the outer part of the shield. After optimization by adding the lead with certain layers, the radiation dose rate decreased, with the largest dose being 57.60 µSv/h. Some locations over the limit could be overcome by other radiation protection aspects such as distance and time. The paraffin blocks were covered by aluminium to keep the shield structure. The lead was used to absorb the gamma ray which resulted from the interaction between the neutrons and aluminium.

Development of New Simulation Software System to Evaluate Radiation Dose Rates in a Wide Radioactively Contaminated Area

2012 ◽  
Author(s):  
Tomoharu Hashimoto ◽  
Masahiro Kondo ◽  
Ryuichi Tayama ◽  
Hideho Gamo
Keyword(s):  
Radiation Dose ◽  
Dose Rate ◽  
Gamma Ray ◽  
Simulation Software ◽  
Radiation Dose Rate ◽  
Dose Rates ◽  
Reduce Radiation Exposure ◽  
Radiation Sources ◽  
Reduction Effect ◽  
Contaminated Area

The Japanese government plans to conduct decontamination tasks in radioactively contaminated areas. For such a situation, we developed a system that evaluates radiation dose rates in a wide radioactively contaminated area by utilizing our radiation dose evaluation technology. This system can not only generate present maps of radiation dose rate in the air based on the dose rate measured at the surface of the contaminated areas, but can also quickly calculate the reduction effect of dose rate due to decontamination tasks by entering decontamination factors. The system can then formulate decontamination plans and make it possible to plan measures to reduce radiation exposure for workers and local residents. Radioactive nuclides that contribute to gamma-ray dose rate are mainly Cs-134 and Cs-137 in soil, on trees, buildings, and elsewhere. Shapes of such radiation sources are assumed to be 10m square or 100m square. If it is unsuitable that the radiation sources assume to squares, the radiation sources can assume to point. The relation between distance from the surface or point source and the radiation dose rate is calculated using MCNP5 code (A General Monte Carlo N-Particle Transport Code - Version 5), and approximated using four-parameter empirical formula proposed by Harima et al. In addition, the system can consider shielding such as soil, concrete, and iron. When setting such shielding, the skyshine dose rate is taken into account in dose rate calculation.

Radon loss from encapsulated sediments in Ge gamma-ray spectrometry for the annual radiation dose determination in luminescence dating

2006 ◽  
Vol 56 (1) ◽  
pp. D183-D194 ◽  
Author(s):  
F. De Corte ◽  
D. Vandenberghe ◽  
A. De Wispelaere ◽  
J. -P. Buylaert ◽  
P. Van den Haute
Keyword(s):  
Radiation Dose ◽  
Gamma Ray ◽  
Luminescence Dating ◽  
Gamma Ray Spectrometry ◽  
Dose Determination

Radon loss from encapsulated sediments in Ge gamma-ray spectrometry for the annual radiation dose determination in luminescence dating

2006 ◽  
Vol 56 (S4) ◽  
pp. D183-D194
Author(s):  
F. De Corte ◽  
D. Vandenberghe ◽  
A. De Wispelaere ◽  
J.-P. Buylaert ◽  
P. Van den Haute
Keyword(s):  
Radiation Dose ◽  
Gamma Ray ◽  
Luminescence Dating ◽  
Gamma Ray Spectrometry ◽  
Dose Determination

A performance comparison of k0-based ENAA and NAA in the (K, Th, U) radiation dose rate assessment for the luminescence dating of sediments

2005 ◽  
Vol 263 (3) ◽  
pp. 659-663 ◽  
Author(s):  
F. De Corte ◽  
M. Dejaeger ◽  
S. M. Hossain ◽  
D. Vandenberghe ◽  
A. De Wispelaere ◽  
...  
Keyword(s):  
Radiation Dose ◽  
Dose Rate ◽  
Performance Comparison ◽  
Luminescence Dating ◽  
Radiation Dose Rate ◽  
A Performance

scholarly journals Terrestrial Gamma Radiation Dose Rate of West Sarawak

2017 ◽  
Vol 156 ◽  
pp. 00006
Author(s):  
A. Izham ◽  
A.T. Ramli ◽  
W.M. Saridan Wan Hassan ◽  
H.N. Idris ◽  
N.A. Basri
Keyword(s):  
Radiation Dose ◽  
Gamma Radiation ◽  
Dose Rate ◽  
Radiation Dose Rate ◽  
Gamma Radiation Dose
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