• 펄프종이기술
• /
• 제42권3호
• /
• pp.43-49
• /
• 2010

Recently, the use of fumigants for pest control of paper cultural heritages are limited because of the high toxicity of fumigants and the production of environment-harmfully compounds. Therefore, many non-chemical methods have been discussed and experimented. And it is recently focused on gamma radiation, which is one of non-chemical methods, for pest control of paper cultural heritage in Korea. In this paper, we carried out a gamma ray irradiation of papers including Hanji, copy paper, filter paper and then analyzed a physical properties and optical properties of paper sample to estimate the effect of gamma ray irradiation on paper properties. In result, gamma radiation have adverse effect on a physical properties and optical properties of paper, especially Hanji. Therefore, we have to carefully consider about using of gamma ray for pest control of paper cultural heritages.

• Journal of Astronomy and Space Sciences
• /
• 제31권4호
• /
• pp.317-323
• /
• 2014

Odyssey, one of the NASA's Mars exploration program and SELENE (Kaguya), a Japanese lunar orbiting spacecraft have a payload of Gamma-Ray Spectrometer (GRS) for analyzing radioactive chemical elements of the atmosphere and the surface. In these days, gamma-ray spectroscopy with a High-Purity Germanium (HPGe) detector has been widely used for the activity measurements of natural radionuclides contained in the soil of the Earth. The energy spectra obtained by the HPGe detectors have been generally analyzed by means of the Window Analysis (WA) method. In this method, activity concentrations are determined by using the net counts of energy window around individual peaks. Meanwhile, an alternative method, the so-called Full Spectrum Analysis (FSA) method uses count numbers not only from full-absorption peaks but from the contributions of Compton scattering due to gamma-rays. Consequently, while it takes a substantial time to obtain a statistically significant result in the WA method, the FSA method requires a much shorter time to reach the same level of the statistical significance. This study shows the validation results of FSA method. We have compared the concentration of radioactivity of $^{40}K$, $^{232}Th$ and $^{238}U$ in the soil measured by the WA method and the FSA method, respectively. The gamma-ray spectrum of reference materials (RGU and RGTh, KCl) and soil samples were measured by the 120% HPGe detector with cosmic muon veto detector. According to the comparison result of activity concentrations between the FSA and the WA, we could conclude that FSA method is validated against the WA method. This study implies that the FSA method can be used in a harsh measurement environment, such as the gamma-ray measurement in the Moon, in which the level of statistical significance is usually required in a much shorter data acquisition time than the WA method.

• 전자공학회논문지
• /
• 제52권4호
• /
• pp.197-203
• /
• 2015

전 세계적으로 전력생산을 위해 원전 증설이 지속적으로 증가하고 있으며 이에 따라 노후 원전에 대한 해체 및 원전사고에 대한 관심이 증가하고 있다. 원전 사고 시 발생되는 감마선원의 누출은 신속하고 정확한 탐지해야 그 피해를 최소화 시킬 수 있다. 기 개발된 장비는 선원에 대한 방향정보만을 나타내고 있어 정확한 공간상의 분포를 알 수 없다. 본 논문에서 개발한 스테레오 감마선탐지장치는 누출된 감마선원에 대한 분포를 측정할 수 있도록 구현하고 거리탐지를 위한 알고리즘을 적용하였다. 거리탐지를 위하여 스테레오 보정을 LED광과 보정패턴을 사용하여 진행하였고, LED 광원과 감마선원을 대상으로 성능시험을 진행하였다. 성능시험 결과 두 실험에서 5%이하의 오차를 갖게 됨을 확인하였다. 본 논문의 결과는 향후 고속 경량화 된 감마선 영상화 장치 개발을 위한 자료로 활용될 것이다.

• 방사선산업학회지
• /
• 제8권2호
• /
• pp.105-109
• /
• 2014

This study was conducted to investigate the sensitivity of Arthrobacter sp. PAMC 25486 to various mutagens. ${\gamma}-ray$, UV-ray, Ethyl methane sulfonate (EMS) and hydrogen peroxide ($H_2O_2$) were used as mutagen, and the survival rate of Arthrobacter sp. was measured at various doses of ${\gamma}-ray$ and UV-ray, and concentrations of EMS and $H_2O_2$. Decimal reduction dose ($D_{10}$ value) of Arthrobacter sp. was determined 370 Gy for a gamma irradiation treatment, 0.019 J for a UV ray, 2.5 mM for EMS, and 230 mM for $H_2O_2$. This result will be applied for the development of superior mutant strain of Arctic bacteria producing valuable compounds.

• 전기의세계
• /
• 제13권3호
• /
• pp.13-20
• /
• 1964

The measurements of X-ray and Gamma-ray Dose Rate have been successfully made by measuring the short circuit current of the Silicon P-N Junction Diode being irradiated. The short circuit current flows when a silicon P-N Junction Diode is irradiated by X-ray of Gammaray radiations due to photovoltaic effect. A brief analysis is given in order to verify the proportionality of a short circuit current to the Dose Rate. Using this method, measurements of X-ray Dose Rate were carried out in the range of 0.05-1600 r/m successfully. The calibration was made by comparing with Victoreen condenser r-meter. Some advantages in this Dose Rate meter over a condenser r-meter were found. One can measure a continous variation of X-ray Dose Rate with this rate meter at the control console of X-ray device.

• 방사성폐기물학회지
• /
• 제2권2호
• /
• pp.97-104
• /
• 2004

NIPS 시스템은 중성자 핵반응 결과 방출되는 즉발 감마선을 정량적으로 측정하는 장치이며 고체 및 액체 폐기물 중 존재하는 다양한 원소를 비파괴적으로 분석할 수 있는 장점이 있다. 본 연구에서는 NIPS 시스템에 이용된 고순도반도체 검출기의 계측효율을 $^{l33}$Ba 및 $^{152}$Eu 방사성 동위원소 선원과 $^{35}$ Cl(n, ${\gamma}$)$^{36}$ Cl 핵반응 시 발생되는 즉발감마선을 이용하여 80 keV에서 8 MeV까지 넓은 영역에 대하여 구하였다. $^{35}$ Cl(n, ${\gamma}$)$^{36}$ Cl 핵반응을 이용한 고에너지 감마선의 계측효율은 즉발감마선의 방사능 값을 정확히 알 수 없기 때문에 저 에너지 영역에서 정확히 알고 있는 검출기 효율곡선에 규격화시켜 전 에너지 영역에서의 효율보정곡선을 구하였다. 또한 KCl 표준용액에 $^{252}$ Cf 중성자 선원을 조사시켜 표준용액으로부터 방출되는 즉발 감마선을 고순도반도체 검출기로 측정하고 광대역 계측효율 곡선을 이용하여 수용액 시료에서의 평균 열중성자 속을 예측하였다. NIPS 측정시스템은 주변 재료 물질의 핵반응으로 방출되는 감마선 background를 줄이기 위해 두 개의 고순도반도체 검출기를 이용한 동시계수 장치가 고안되었으며, 동시계수 모드에서의 계측효율도 함께 고려되었으며, 표준선원을 이용하여 전 계수 또는 동시계수모드에서의 background에 대한 측정감도를 비교하였다.다.

• 한국작물학회지
• /
• 제7권1호
• /
• pp.139-144
• /
• 1969

본실험은 대두품종 장단백일과 Clark의 건조종자에 ${\gamma}$선, EMS, EI, 및 ${\gamma}$선과 화학약품과의 조합처리로써 조열, 내도복, 고단백, 다수성 등 유용한 돌연변이계통을 선발할 목적으로 수행하였는데 기초자료로써 처리상대의 돌연변이유기물에 대한 감수성을 조사하였다. 1. ${\gamma}$선의 조사는 장단백일에서 선량증가에 따라 발아 및 생잔율에 큰 장해를 주었으나 Clark에서는 일정한 경향을 찾아 볼 수 없었다. EH한 초장에 있어서는 양 품종 모두 선량이 증가 할수록 고도의 유의성이 있는 생장장해를 보였다. 2. Chemical mutagens을 처리한 경우는 양 품종 똑같이 Ei의 농도가 증가함에 유의성있게 발아율이 감소되었으며 특히 EI의 0.003 Mol. 농도에선 아주 극심한 장해를 나타내고 있다. EMS처리는 발아와 생잔율에 유의성있는 변화를 주지 못했으나 초장에서 장단백일은 농도가 증가함에 따라 유의적인 생육장해가 나타났다. Clark에선 일정한 경향을 찾아 볼 수 없었다. 3. ${\gamma}$선 24KR과 FMS 각 농도를 조합처리한 것은 EMS 단독처리 보다 유의하게 발아율이 떨어졌으며 EI과의 조합처리구에서는 ${\gamma}$선 24KR+EI 0.002 Mol을 제외한 각조합처리의 발아율은 EI 단독처리보다 오히려 양호한 결과를 나타냈다. 생잔율에서는 뚜렷한 경향을 찾지 못하였으나 초장에선 ${\gamma}$-선 24KR+EMS 각 농도조합과 그 단독처리구를 비교할 때, 양 품종 모두 고도의 유의차로 조합처리가 생육장해정도를 크게 나타냈다. EI와 ${\gamma}$-선 조합처리가 저농도에서는 초장의 감소를 나타냈으나 ${\gamma}$-선24KR+EI 0.008Mol. 처리구에선 장단백일의 파종후 21일만 제외하고 단독처리구 보다 초장이 증가하는 경향이 나타났다. 4. 일반적으로 본 실험에선 발아율과 생잔율이 EMS 단독 및 ${\gamma}$-선+EMS 처리구에서 양호한 결과를 보았으며 EI 및 ${\gamma}$-선+EI 처리구에선 그 고농도구에서 발아율을 감소시켰으나 초장에 나타나는 생육장해는 적었고 오히려 촉진되는 경향도 있었다. 5. 발아율, 생잔율 및 초장을 기준으로 한 감수성을 비교해 보건데 대체적으로 장단백일은 Clark에 비해 매감하였으며 이는 그 감수성이 유전인자구성에 따라 크게 차이를 줄 수 있다는 것을 입증하고 있다.

• 환경위생공학
• /
• 제13권2호
• /
• pp.106-114
• /
• 1998

This study was carried out for the purpose of industrial reuse of effluent released from activated sludge unit by $\gamma $-ray irradiation technique. The dissolved organic carbon in the effluent of an activated sludge unit is mostly refractory or inert material which are difficult to be degraded by micro organism. The effluent generated from activated sludge unit was irradiated with Co$^{60}$ $\gamma $-ray under condition of air bubbling. The effects of irradiation on the pH, COD, TOC, color, molecular weight distribution were investigated by membrane filtration and u.v.-spectrum analysis. With increasing dose, the TOC was decreased smoothly. The COD was increased at lower dose, while the COD was decreased at higher dose. The TOC and COD, however, were decreased smoothly when TiO$_{2}$ was added to the solution. It was thought that the differential decreasing trend of COD and TOC in according to the absence or presence of TiO$_{2}$ was due to the molecular weight distribution shifted from group of higher molecular weight to group of lower one which are more easy to be decomposed. The removal efficiency of color was 71.5% and it was increased to 85.7% when TiO$_{2}$ was added to the solution. The $\gamma $-ray irradiation was effective on the production of chlorine.

• Nuclear Engineering and Technology
• /
• 제38권4호
• /
• pp.383-390
• /
• 2006

Having its roots in medical applications, industrial gamma ray CT has opened up new roads far investigating and modeling industrial processes. Using a line of research related to industrial gamma ray CT, the authors set up a system of single source and detector gamma transmission tomography for wood timber and a packed bed phantom. The hardware of the CT system consists of two servo motors, a data logger, a computer, a radiation source and a radiation detector. One motor simultaneously moves the source and the detector for a parallel beam scanning, whereas the other motor rotates the scan table at a preset projection angle. The image is reconstructed from the measured projections by the filtered back projection method. The phantom was designed to simulate a cross section of a packed bed with a void. The radiation source was 20mCi of Cs-137 and the detector was a 1 inch $\times$ 1 inch NaI (TI) scintillator shielded by a lead collimator. The experimental gamma ray CT image has sufficient resolution to reveal air holes and the density distribution inside the phantom. The system could possibly be applied to a packed bed column or a pipe flow in a petrochemical plant.

• Nuclear Engineering and Technology
• /
• 제49권4호
• /
• pp.792-800
• /
• 2017

The essential requirement of a material to be used for engineering purposes at nuclear establishments is its ability to attenuate the most penetrating ionizing radiations, gamma $({\gamma})-rays$. Mostly, high-Z materials such as heavy concrete, lead, mercury, and their mixtures or alloys have been used in the construction of nuclear establishments and thus termed as nuclear engineering materials (NEM). The NEM are classified into two categories, namely opaque and transparent, depending on their behavior towards the visible spectrum of EM waves. The majority of NEM are opaque. By contrast, various types of glass, which are transparent to visible light, are necessary at certain places in the nuclear establishments. In the present study, ${\gamma}-ray$ shielding behaviors (GSB) of six glass samples (transparent NEM) were evaluated and compared with some opaque NEM in a wide range of energy (15 keV-15 MeV) and optical thickness (OT). The study was performed by computing various ${\gamma}-ray$ shielding parameters (GSP) such as the mass attenuation coefficient, equivalent atomic number, and buildup factor. A self-designed and validated computer-program, the buildup factor-tool, was used for various computations. It has been established that some glass samples show good GSB, thus can safely be used in the construction of nuclear establishments in conjunction with the opaque NEM as well.