• Korean Journal of Crystallography
• /
• v.15 no.2
• /
• pp.99-103
• /
• 2004

The structure of $C_{16}H_{19}O_2N_3CuCl_2\;{\cdot}\;H_2O$ has been determined by X-ray diffraction methods. The crystal system is triclinic, space group Pl, unit cell constants. $a=7.6202(9)\; \AA,\; b=8.5943(7) \AA,\; c= 8.6272(6) \AA,\; \alpha= 67.518(6)^{\circ}.\; \beta= 68.043(8)^{\circ},\; \gamma=74.370(8)^{\circ},\; V=478.89(8)\; \AA^3,\; T=295K,\; Z=1,\; D_c=1.504Mgm^{-3}$The intensity data were collected on an Enraf-Nonius CAD-4 Diffractometer with graphite monochromated $MoK\alpha$ radiation $(\alpha=0.7107\;\AA)$. The molecular structure was solved by direct method.』 and refined by full-matrix least squares to a final $R=2.47\%$ for 1659 unique observed $F_0>4\sigma(F_0)$ reflections and 234 parameters.

• Nuclear Engineering and Technology
• /
• v.55 no.5
• /
• pp.1587-1592
• /
• 2023

Time-encoded imagers (TEI) are important class of instruments to search for potential radioactive sources to prevent illicit transportation and trafficking of nuclear materials and other radioactive sources. The energy of the radiation cannot be known in advance due to the type and shielding of source is unknown in practice. However, the response function of the time-encoded imagers is related to the energy of neutrons or gamma-rays. An improved image reconstruction method based on MLEM was proposed to correct for the energy induced response difference. In this method, the count vector versus time was first smoothed. Then, the preset response function was adaptively corrected according to the measured counts. Finally, the smoothed count vector and corrected response were used in MLEM to reconstruct the source distribution. A one-dimensional dual-particle time-encode imager was developed and used to verify the improved method through imaging an Am-Be neutron source. The improvement of this method was demonstrated by the image reconstruction results. For gamma-ray and neutron images, the angular resolution improved by 17.2% and 7.0%; the contrast-to-noise ratio improved by 58.7% and 14.9%; the signal-to-noise ratio improved by 36.3% and 11.7%, respectively.

• Nuclear Engineering and Technology
• /
• v.56 no.11
• /
• pp.4921-4928
• /
• 2024

The present study employed statistical methods to evaluate the possible radiological hazards linked to granitic rocks-bearing mineralization in the ELgarra region of Egypt. The geological structures influence the occurrence of uranium mineralization in this area and are primarily associated with altered granites. Gamma-ray spectrometry was utilized to examine the quantities of ²³⁸U, ²³²Th, and ⁴⁰K in granitic rock samples. The recorded levels of radioisotope activity concentrations in the analyzed regions ranged from 374 to 1740 Bq.kg^{-1 238}U, with an average of 1018 Bq.kg^-1. For ²³²Th, the range was between 71 and 163 Bq.kg^-1, with an average of 119 Bq.kg^-1. Lastly, for ⁴⁰K, the range was 756-1789 Bq.kg^-1, with an average of 1212 Bq.kg^-1. The detected levels of ²³⁸U, ²³²Th, and ⁴⁰K in the examined rock samples were observed to exceed the permissible limits of 35, 45, and 412 Bq.kg^-1, respectively. The primary radiological risks linked to these granitic rocks were attributed to the gamma rays released by the radioactive elements. Estimations of the radiological hazards in the granitic rocks were made, and statistical approaches were utilized to demonstrate the associations among radionuclides and radiological factors. The assessment confirmed that uranium, potassium, and their respective minerals in the granitic rocks were the key factors contributing to the radiological risks. As a result, the study determined that the granite rocks found in the study area needed precautions to be taken due to their high levels of radioactivity.

• Progress in Medical Physics
• /
• v.1 no.1
• /
• pp.91-95
• /
• 1990

The solid state detector system was constructed using commercially available rectifier diode for the assessment of quality assurance in radiotherapy. Dosimetry system which consists of the electrometer and the water phanton was used for measuring small field size scanning. The measured results, which had linearity in accordance with variation of radiation dose for gamma-ray of Co- 60 and 6 and 10MV photons of linear accelerator, showed quite linear characteristics within 1% error. The percent depth dose of 10MV photon of Mevatron KD linear accelerator was measured in small field size using diode, and the results were compared with that of using ion chambers. The results show that the difference of percent depth dose between the value of diode and that of ion chamber was negligible in large field size. However, in small size less than 4$\times$4cm, the difference of percent depth dose estimated by diode and ion chamber was 4.7% by extrapolation to 0$\times$0cm. Considering the smaller volume of diode than that of ion chamber, it might be more reliable to use diode for estimating percent depth dose. Above results suggest that diode can be used for routine check such as beam profile, flatness, symmetry and energy

• Proceedings of the KIEE Conference
• /
• 2009.07a
• /
• pp.1788_1789
• /
• 2009

본 논문에서는 핵폭발과 같은 고준위방사선환경에서의 전자부품소자의 피해평가분석을 통하여 군용전자장비의 내방사선화를 하기 위한 기반기술의 확립을 위한 연구의 일환으로 74AC04(Inverter) IC에 대한 고준위감마선조사시험을 통하여 Co-60 Gamma-ray 선원을 사용하여 총 400Krad[si] 누적 선량에 대한 74AC04 소자의 동작특성 및 전기적 파라메터의 변화분석을 진행하였다. 시험평가 방법 및 절차는 MIL-STD-883G 1019.7[1] 및 ESA/SCC Basic Specification No.22900[2] 절차를 기준으로 하여 동일 lot에 대한 5개의 샘플을 이용하여 동작특성에 영향을 미치는 주요한 전기 적파라메터인 정지소비전류, 입력누설전류, VIL(Maximum Low Level Input Voltage)에 대한 변화추이를 분석하였다. 이번 조사시험을 통하여 입력게이트에서의 누적선량에 따른 TID(Total Ionizing Dose) 효과로 인한 VIL의 감소 추이를 확인 할 수 있었으며 총 누적선량 160Krad 이상에서의 VIL은 허용기준치이하로 감소하였고 정지소비전류의 경우 누적선량에 따른 점진적 증가 현상과 200Krad부근에서의 설계스펙허용치를 초과하는 결과를 확인하였다.

• Nuclear Engineering and Technology
• /
• v.52 no.6
• /
• pp.1282-1288
• /
• 2020

In the first study, the Radon emanation and radiological hazards associated with radionuclides in soil samples, collected from 9 various date palm farms located in 3 different districts in Saudi Arabia were determined through a high purity Germanium (HPGe) gamma-ray spectrometer. The estimated average values of Radon emanation coefficient and Radon mass exhalation rate for soil samples were 0.535 ± 0.016 and 50.063 ± 7.901 mBqkg^-1h^-1, respectively. The annual effective dose of radionuclides in all sampling locations was found to be lower than UNSCEAR's recommended level of 0.07 mSvy^-1 for soil in an outdoor environment. In the secondary study, gross α and gross β activities in soil and date palm pits samples were measured by a low background α/β counting system. Average values of gross α and gross β activities in soil and date palm pits samples were 5.761 ± 0.360 Bqkg^-1, 38.219 ± 8.619 Bqkg^-1 and 0.556 ± 0.142 Bqkg^-1, 24.266 ± 1.711 Bqkg^-1, respectively.

• Korean Journal of Microbiology
• /
• v.52 no.4
• /
• pp.500-502
• /
• 2016

Several bacterial species have been reported to be surviving after the ionizing radiation treatment due to the presence of sophisticated enzymes systems and some endospores producing bacterial strains can also resist, due to the presence of thick spore coat. In this study, we report the complete genome sequence of a bacterium Paenibacillus swuensis $DY6^T$, isolated from an irradiated soil sample. The genome comprised of 5,012,599 bp with the G+C content of 49.93%, the genome included 4,463 protein coding genes and 133 RNA genes.

• Nuclear Engineering and Technology
• /
• v.20 no.1
• /
• pp.65-70
• /
• 1988

A Shielding analysis of the shipping cask designed conceptually, of which shielding material are lead and resin, for containing 4 PWR spent fuel assemblies, has been made with the help of a computer code, ANISN. The shielding materials being used in the cask have been selected and arranged to minimize cask weight while maintaining an overall shielding effectiveness. Radiation source terms have been calculated by means of ORIGIN-2 code under the assumptions of 38,000 MWD/MTU burnup and 3-year cooling time. A calculation of gamma-ray and neutron dose rates on the cask surface and 1m from the surface has been done. It is revealed that the total dose rates under the normal transport and hypothetical accident conditions meet the standards specified.

• Journal of the Korean Society of Radiology
• /
• v.9 no.2
• /
• pp.73-77
• /
• 2015

In order to observe the detailed structure of the detector, it was CT scanned to reproduce the detailed structure of the crystal shapes and traverse layer using the Monte Carlo calculation applying the detector model. The uncertainty of measurement was lowered by adjusting the detector core by the edge effect at a higher energy (400 keV or higher) through the offset of peak efficiency of the gamma ray at low energy. It was confirmed that there was the appropriate matching with spatial dependency using the PENELOPE calculation. That was achieved by adjusting the parameters describing the crystal core and rounding of edge and crystal core.

• The Korean Journal of Nuclear Medicine
• /
• v.24 no.2
• /
• pp.307-316
• /
• 1990

Irradiation is widely used for the treatment of malignant diseases, and possibly cause the osteoporosis. The densitometry and bone scintigraphy are valuable when used to monitor the patients longitudinally to access the progression of osteoporosis and risk of osteoradionecrosis. To evaluate the osteoporosis after irradiation of Cobalt-60 gamma ray on the lumbar spines of New Zealand white rabbits, bone densitometry by dual photon absorptiometry and bone scintigraphy were performed weekly. The decrease of bone density began at the first week after irradiation, and were in the nadir at 4-6th week. The osteoblastic activity measured by bone scintigraphy decreased in the first week, and was in the nadir at 4-6th week. The severity of these changes were related to the radiation dose. In conclusion, the osteoporosis before the presentation of the osteoradionecrosis can be diagnosed early with the dual photon absorptionmetry and bone scintigraphy.