• Journal of Radiation Protection and Research
• /
• v.22 no.3
• /
• pp.219-226
• /
• 1997

Ultralow background gamma-ray measurement system was installed to measure and analyze gamma-rays emitted from environmental and swipe samples. The background reduction techniques applied on this system are the passive shielding to surround the HPGe detector, an active external anticosmic shield to shield cosmic-rays and the nitrogen gas supply to minimize the introduction of ubiquitous radon decay nuclei. The performance test result showed that the system background at energies between 50 keV and 2 MeV is reduced about $10^{-2}$ order and the MDA is so low as to be suitable for the environmental sample analysis. But it is appeared that the neutron produced by cosmic-ray increases the background at low energy region.

• Journal of the Korean Society of Food Science and Nutrition
• /
• v.36 no.4
• /
• pp.453-457
• /
• 2007

The physicochemical properties of red beets and the stability of betalain pigments irradiated at 2.5, 5, 10 and 30 kGy were evaluated. Betalain extraction yield of irradiated red beets was not significantly different from non-irradiated red beet. The red beet irradiated at 5kGy showed high optical density value in betacyanin and betaxanthin. In Hunter's color value lightness (L), redness (a) and yellowness (b) decreased with increment of irradiation dose. All red beets showed no difference in pH. The red beets irradiated above 10 kGy had poor textural property quality but antioxidant activity of betalain was not significantly changed by gamma irradiation. Considering natural colorant and textural quality, the gamma irradiation above 10kGy was an undesirable technique for red beets.

• Journal of the Korea Institute of Information and Communication Engineering
• /
• v.16 no.10
• /
• pp.2287-2292
• /
• 2012

In this study, $Co^{60}$ gamma-ray induced loss on Ge-doped single mode (SM) fiber has been measured. Gamma-ray is irradiated for 4 hours at the dose rate of 0.5 kGy/hr, 2 kGy/hr, 8 kGy/hr. Consequently, gamma-ray induced loss based on radiation effects in Ge-doped SM fiber occur significantly. Furthermore, dose rate effect was observed, that dose rate using the same total dose increased higher, then optical fiber loss increased more. Also annealing effect was observed, that the loss after irradiation, increased higher, then the recovery rate of loss was increased. This results are foreseen to be base data in the future radiation-hardened optical fiber study.

• Food Science and Preservation
• /
• v.14 no.4
• /
• pp.408-413
• /
• 2007

This study evaluated the sensory quality characteristics of gamma-irradiated Sujeonggwa a Korean traditional cinnamon beverage during storage, and the mutagenicity of the beverage. The minimum irradiation dose required to ensure the microbiological safety of powdered Sujeonggwa was 4.5 kGy. Sensory characteristics, and the Hunter's color value, of Sujeonggwa, deteriorated with increased irradiation doses, but no significant changes in sensory qualities were found during storage. The Ames test yielded no evidence that gamma irradiation induced mutagenicity in Sujeonggwa powder.

• Korean Journal of Food Science and Technology
• /
• v.32 no.5
• /
• pp.1102-1106
• /
• 2000

This study was carried out to investigate the effects of gamma irradiation for the improvement of hygienic quality and the extension of shelf-life of Kwamegi(semi-dried colobabis seira). Kwamegi was stored at $5^{\circ}C$ and $15^{\circ}C$ after gamma irradiation with doses of 0, 3, 5, 7 and 10 kGy. In microbiological aspects, non-irradiated Kwamegi was rapidly deteriorated during storage, and some harmful bacteria were detected in a microbial analysis using a selective medium. However, the total viable cells and presumptive pathogens were reduced with the increase of irradiation dose, and dose level of 7 to 10 kGy was considered to be optimum and effective dose for the preservation of Kwamegi.

• Journal of radiological science and technology
• /
• v.45 no.1
• /
• pp.57-67
• /
• 2022

CZT detectors, which are compound semiconductors that have been widely used recently for gamma-ray detection purposes, are difficult to detect neutrons because direct interaction with them does not occur unlike gamma-rays. In this paper, a method of detecting and determining energy levels (fast neutrons and thermal neutrons) of neutrons, in addition of identifying energy and nuclide of gamma-rays, and evaluating gamma dose rates using a CZT semiconductor detector is described. Neutrons may be detected by a secondary photoelectric effect or compton scattering process with a characteristic gamma-ray of 558.6 keV generated by a capture reaction (¹¹³Cd + ¹n → ¹¹⁴Cd + 𝛾) with cadmium (Cd) in the CZT detector. However, in the case of fast neutrons, the probability of capture reaction with cadmium (Cd) is very low, so it must be moderated to thermal neutrons using a moderator and the material and thickness of moderator should be determined in consideration of the portability and detection efficiency of the equipment. Conversely, in the case of thermal neutrons, the detection efficiency decreases due to shielding effect of moderator itself, so additional CZT detector that do not contain moderator must be configured. The CZT detector that does not contain moderator can be used to evaluate energy, nuclide, and gamma dose-rate for gamma-rays. The technology proposed in this paper provides a method for detecting both neutrons and gamma-rays using a CZT detector.

• Journal of Radiation Protection and Research
• /
• v.38 no.2
• /
• pp.119-123
• /
• 2013

A simple laboratory-made radioactive source to check the integrity of a gamma spectrometry system with HPGe detector was developed. The check source consists of radium-riched soil which was ground in size of less than 0.154mm and contained in air tight cylinderical vial, and provides photons with 12 distinct energies. The spectra of the check source were measured once a month during one year, analyzed the charactreictics of their peaks. When the gamma spectrometry system was in normal state, the areas and FWHMs of the gamma rays with more than 3% gamma emission rate in radium and its decay products was constant within standard deviation 2% and 3%, respectively, except 77 keV peak. And it was found that this check source can play a sufficient role to check the integrity of a gamma spectrometry system using 10 peaks in the range of 77 to 2202 keV.

• Journal of the Korean Society for Nondestructive Testing
• /
• v.22 no.5
• /
• pp.500-507
• /
• 2002

By this study, on-line real-time radiometric system was developed using a 64 channels linear array of solid state detectors to measure wall thickness of insulated piping system. This system uses an Ir-192 as a gamma ray source and detector is composed of BGO scintillator and photodiode. Ir-192 gamma ray source and linear detector array mounted on a computer controlled robotic crawler. The Ir-192 gamma ray source is located on one side of the piping components and the detector array on the other side. The individual detectors of the detector array measure the intensity of the gamma rays after passing through the walls and the insulation of the piping component under measurement. The output of the detector array is amplified by amplifier and transmitted to the computer through cable. This system collects and analyses the data from the detector array in real-time as the crawler travels over the piping system. The maximum measurable length of pipe is 120cm/min. in the case of 1mm scanning interval.

• Analytical Science and Technology
• /
• v.14 no.3
• /
• pp.212-220
• /
• 2001

This study was performed to establish the analytical method of radium and radon in various environmental samples with the ${\gamma}$-ray spectrometry. The major problem in the measurements of low level ${\gamma}$-ray, such as environmental radioactivity, is the fluctuation of ${\gamma}$-ray background spectrum. To overcome this problem, a nitrogen gas was filled up in the detector chamber to reduce the background counts due to airborne radioactivities, i.e., $^{214}Pb$ and $^{214}Bi$, the daughters of $^{222}Rn$ in air. When nitrogen gas flowed around the detector, peak counts of ${\gamma}$-rays from the daughters of $^{222}Rn$ decreased about 80% below 1 MeV and about 20~50% above 1 MeV. The use of nitrogen purging results in approximately tenfold increment of sensitivity.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.05b
• /
• pp.752-756
• /
• 1998

산업용 및 의료용으로 사용되는 $^{192}$ Ir 방사선원에 대한 $\psi$선 자기흡수효과인자를 실험을 통하여 구하였다. 이를 위하여 3 mm $\psi$ x 3 mm t, 2.5 mm $\psi$ x 2.5 mm t, 2 mm $\psi$ x 2 mm Ir의 원주형 Ir 표적과 3 mm $\psi$ x 0.25 mm t, 3 mm $\psi$ x 0.1 mm t의 원판형 Ir 표적을 하나로의 PTS(Pneumatic Transport System)조사공에서 중성자 조사하였다. 이온전리함을 사용하여 각 Ir 표적의 방사능을 측정하고 계산에 의해서 구한 생성방사능 값과의 비를 구하는 방법으로 $^{192}$ Ir의 ${\gamma}$선 자기흡수효과인자를 구하였다. 이 값들은 원주형 표적에 대하여 각각 0.614, 0.687, 0.704 였고 원판형 표적에 대하여 각각 0.827, 0.875 였다. 원주형 Ir 표적내부의 중성자 자기흡수효과의 정도를 알아보기 위하여 2.5 mm $\psi$ x 0.25 mm t Ir 표적 10장을 포개어 중성자 방사화시킨 후 각 표적의 방사능을 측정한 결과 가장 바깥쪽 표적의 방사능이 중심부에 위치한 표적보다 약 2배정도 방사화가 많이 일어남을 알 수 있었다. 이번에 구한 ${\gamma}$선 자기흡수효과인자는 향후 산업용 및 의료용으로 사용되는 $^{192}$ Ir 방사선원의 사용자에게 제공되는 최종방사능을 평가하는데 유용하게 사용될 수 있다.