• 한국식품위생안전성학회지
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• 제1권1호
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• pp.57-66
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• 1986

Campylobacter jejuni has been recognized as one of the causes of human gastroenteritis. The feces of a variety of reservoir animals contain c. jejuni as commensals in the intestinal tracts, and are fundamental source of contamination. The intestinal organisms contaminate carcasses, equipment tools hands of the processing line workers and air of the processing facility. Once the contamination happens in the slaughterhouses or the meat processing facilities, it is very difficult to keep the carcasses free from the infection of c. jejuni. Various disinfectants are effective in minimizing the number of Campylobacter infections in the processing facilities by washing contaminated carcasses, tools, and hands. Direct contact with infected animals has been incriminated in transmission of infection caused by C. jejuni. Freezing, cooling with dry air and gamma irradiation are an effective way for preserving the meat and eliminating the transmission, but broad and enforced studies are needed for the practical use.

• Nuclear Engineering and Technology
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• 제29권2호
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• pp.175-180
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• 1997

It has been known that eater-side corrosion of fuel rods in nuclear reactor is accompanied with the metallic loss of wall thickness and hydrogen pickup in the fuel dadding tube. The fuel dad corrosion is one of the major factors to be controlled to maintain the fuel integrity during reactor operation. An oxide later thickness measuring device equipped with ECT probe system was developed by KAERI, and whose performance test was carried out in NDT(Non-destructive Test) hot-cell or PIE(Post Irradiation Examination) Facility. At first, the calibration/performance test was executed for the unirradiated standard specimen rod fabricated with several kinds of plastic thin films whose thickness ore predetermined, and the result of which showed a good precision within 10% of discrepancy. And then, hot test us peformed for the irradiated fuel rod selectively extracted from J44 fuel assembly discharged from Kori Unit-2. The data obtained with this device were compared with the metallographic result obtained from destructive examination in PIEF hot-cell on the same fuel rod to verify the validity of the measurement data.

• Nuclear Engineering and Technology
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• 제38권5호
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• pp.423-426
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• 2006

A developed neutron activation analysis(NAA) and gamma-spectrometry were applied to improve the analytical sensitivity and precision of impurities in electronic-circuit raw materials. It is well known that soft errors in high precision electronic circuits can be induced by alpha particles emitted from naturally occurring radioactive impurities such as U and Th. As electronic circuits have recently become smaller in dimension and higher in density, these alpha-particle emitting radioactive impurities must be strictly controlled. Therefore, new NAA methods have been established using a HTS(Hydraulic Transfer System) irradiation facility and a background reduction method. For eliminating or stabilizing fluctuated background caused by Rn-222 and its progeny nuclides in air, a nitrogen purging system is used. Using the developed NAA and gamma-spectrometry, ultra trace amounts of U(0.1ng/g) and Th(0.01ng/g) in an alumina ball and high purity silica used for an epoxy molding compound (EMC) could be determined.

• 대한전자공학회:학술대회논문집
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• 대한전자공학회 2009년도 정보 및 제어 심포지움 논문집
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• pp.159-162
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• 2009

The necessity of radiation dosimeter with precise measurement of radiation dose is increased and required in the field of spacecraft, radiotheraphy hospital, atomic plant facility, etc. where radiation exists. Until now, a low power commercial metal-oxide semiconductor(MOS) transistor has been tested as a gamma radiation dosimeter. The measurement error between the actual value and the measurement one can occur since the MOSFET(MOS field-effect transistor) dosimeter, which is now being used, has two gates with same width. The measurement value of dosimeter depends on the variation of threshold voltage, which can be affected by the environment such as temperature. In this paper, a radiation dosimeter having a pair of MOSFET is designed in the same silicon substrate, in which each of the MOSFETs is operable in a bias mode and a test mode. It can measure the radiation dose by the difference between the threshold voltages regardless of the variation of temperature.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1997년도 춘계학술발표회논문집(2)
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• pp.427-432
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• 1997

Boron neutron capture therapy(BNCT) is a binary treatment modality that can selectively irradiate tumor tissue. More is known now about the radiation biology of BNCT, which has reemerged as a potentially useful method for preferential irradiation of tumors. We design a square reactor (that can easily be reconfigured into polygonal reactors as the need arises) with four slab type assemblies to produce high quality epithermal neutron beans and thermal neutron beams jot use in neutron capture therapy. With a low operating power of 300kW, the heat generated in the core can be removed by natural convection through a pool of tight water. The proposed design in this study could be constructed for a dedicated clinical BNCT facility that would operate very safely.

• 약학회지
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• 제7권4호
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• pp.75-85
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• 1963

Radioactivation analysis is based upon irradiation of nuclei with elementary particles. In many cases the interaction gives rise to radioactive nuclei, which can be detected and identified by the emitted radiation. If we irradiate under identical conditions an unknown quantity of a certain atomic species and a known quantity of the same species, the following relatio will exist between the induced radioactivities and the irradiated masses: $\frac{Activity standard}{activity unknown}$=$\frac{Mass standard}{Mass unknown}$ From this equation the mass of the unknown can be easily calculated. This relatively siple technique (abstract made from the irradiating facility) allows quantitative determination of about 60 elements with a sensibility that most of the time considerably exceeds the sensibility of conventional analysis techniques. General review articles from Gordon and Meinke should be consulted for further detail.

• Nuclear Engineering and Technology
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• 제55권4호
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• pp.1210-1217
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• 2023

The assessment of radiation fields in the lithium loop pipes and dump tank during the operation were performed for International Fusion Materials Irradiation Facility - DEMO-Oriented NEutron Source (IFMIF-DONES) in order to obtain the radiation dose-rate maps in the component surroundings. Variance reduction techniques such as weight window mesh (produced with the ADVANTG code) were applied to bring the statistical uncertainty down to a reasonable level. The biological dose was given in the study, and potential shielding optimization is suggested and more thoroughly evaluated. The MCNP Monte Carlo was used to simulate a gamma particle transport for radiation shielding purposes for the current Li Systems' design. In addition, the shielding efficiency was identified for the Impurity Control System components and the dump tank. The analysis reported in this paper takes into account the radiation decay source from and activated corrosion products (ACPs), which is created by d-Li interaction. As a consequence, the radiation (resulting from ACPs and Be-7) shielding calculations have been carried out for safety considerations.

• 분석과학
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• 제18권1호
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• pp.5-12
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• 2005

고정밀 전자소자의 오동작의 한 원인인 soft error는 원료물질에 함유된 U, Th과 같은 알파방출 불순물로 알려져 있으며 전자소자의 소형화, 고집적화에 따라서 이들 불순물의 규제함량은 기존의 분석법으로는 불가능할 정도로 낮아지고 있다. 연구의 목적은 다양한 전자소자의 밀봉소재로 사용되는 EMC (epoxy molding compound)의 주 원료인 고순도 실리카에 함유되어 있는 U, Th을 고감도 (ng/g이하)로 분석할 수 있는 방사화분석법과 감마선분광분석법의 개발이다. 지금까지 방사화분석법에 이용하던 PTS (pneumatic transfer system) 중성자 조사 설비로는 산업계에서 요구하는 분석 감도를 충족시킬 수 없기 때문에 의약용 혹은 산업용 RI 생산에 주로 사용되고 있는 HTS (Hydraulic transfer system) 중성자 조사 설비를 이용한 방사화분석 조건을 확립하였다. 또한, 공기중 라돈 ($^{222}Rn$)과 자핵종 (progenies)에 의한 불안정한 바탕방사능은 분석의 감도는 물론 정확도를 저하시키는 주 요인으로 작용하므로 질소가스 유입시스템을 제작하여 라돈에 의한 바탕방사능을 소멸 혹은 안정화시켰다. 그 결과 U과 Th의 분석한계를 각각 0.1 ng/g, 0.01 ng/g까지 낮출 수 있었다.

• 한국정보통신학회논문지
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• 제20권12호
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• pp.2410-2416
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• 2016

전 세계적으로 비핵화를 추구하고 있으나 북한의 계속되는 핵실험 등으로 핵폭에 대한 관심이 지속적으로 증가하고 있다. 핵 폭발 또는 우주환경에서의 발생되는 펄스형 감마선은 매우 짧은 시간동안 고에너지를 전달하기에 전자소자에 큰 피해를 줄 수 있다. 이러한 전자소자의 피해정도를 확인하기 위한 연구를 수행하려면 핵폭 또는 우주환경에서 발생할 수 있는 펄스형 감마선 조사시설이 필요하다. 본 논문에서는 펄스형 감마선 탐지 장치을 개발하고, 감마선 변환장치를 통해 펄스형 감마선을 생성한 후 그 출력을 분석하였다. 핵폭과 유사한 조건을 갖추기 위하여 포항가속기 연구시설의 전자빔가속장치를 이용하여 출력을 실험하였고, 그 결과 감마선 변환장치와 전지빔을 통해 생성한 펄스형 감마선의 방출과 그 출력특성을 확인하였다. 본 논문의 결과는 펄스감마선을 이용해야 하는 연구의 안정성과 정확성을 향상시키는데 기여할 것이다.

• 한국광학회지
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• 제1권2호
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• pp.210-216
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• 1990

본 연구에서는 레이저와 치아조직과의 상호작용에 대한 연구의 일환으로, $CO_2$ 레이저의 발진파장인 $10.6\mu\textrm{m}$의 레이저 빔 조사시에 일어나는 치아의 온도변화를 조사하기 위하여 $CO_2$ 레이저 발진장치를 제작하여 여러 가지 조사 에너지, 조사시간에 대하여 발거된 치아의 치수강의 온도변화를 측정 분석하였다. 측정한 data를 분석하여 최대 상승온도 $\DeltaT_m$를 추정할 수 있는 다음과 같은 실용적인 경험식을 얻었다. $\DeltaT_m=\alphaP\Delta\tauexp(-\betad)$$ 여기서 P는 레이저의 출력(W)이고 $\Delta\tau$는 조사시간(sec), d는 치아의 두께(mm)이다.