• The Science & Technology
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• s.511
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• pp.80-83
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• 2011

정부는 지난 10월, 사상 처음으로 정부 기구의 하나로 '원자력안전위원회'를 설립했다. 후쿠시마 원전 사고 이후, 뒤늦게나마 그 필요성을 절감한 때문이다. 그 '원자력 안전'의 뒤안길에는 1961년, 우리나라에 최초의 연구용원자로 건설에 참여한 이후 50년여 세월을 '원자력의 안전과 산업화'를 주창하며 그 일에만 매달려온 우리나라 원자력 1세대인 임용규 박사(78)가 있다. 정부 수립 직후 출범한 원자력청의 연구관을 시작으로 주미대사관 초대과학관, 국립과학관장, 과학기술부 원자력위원, 한국원자력안전기술원장 등을 역임하였고, 지금도 한국원자력안전아카데미 이상장으로 행공학을 하는 후학들을 격력하고 있는 임용규 박사를 서울 강남에 있는 아카데미에서 만났다.

• Journal of radiological science and technology
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• v.40 no.3
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• pp.501-508
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• 2017

The purpose of present research is to offer a specialized educational opportunity for potential users, university students in radiology, by developing specific curriculum on site at KAERI, using HANARO research reactor and National radiation research facilities. The specific items of this research accomplished are: First, Development and operation of various curricula for specific research using HANARO and National radiation research facilities to provide university students with opportunities to use the facilities. Second, Operation of the experiment training programs for university students in radiology to foster next generation specialists. Third, through the on-site experiment training for students in radiology, support future potential experts of the radiation research fields, and broaden the base. A textbook and a teaching aid, a questionnaire have been developed to support the program. 714 university students have completed the courses for radiology experiment from 2006 to 2017. It is hoped that these experiments broaden public awareness and acceptance by the present and potential future utilization of the research reactor and national radiation research facilities, thereby bring positive impacts to policy making.

• Journal of the Mineralogical Society of Korea
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• v.20 no.4
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• pp.351-356
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• 2007

The crystal structure of $Li(ND_4)SO_4$ was analyzed by X-ray and neutron diffraction methods. The crystal is a deuterated $Li(NH_4)SO_4$ and one of the ferroelectric materials with hydrogen atoms. The crystal is orthorhombic at room temperature, $P2_1nb$, with lattice parameters of $a=5.2773(5)\;{\AA},\;b=9.1244(23)\;{\AA},\;c=8.7719(11)\;{\AA}$ and Z=4. Neutron intensity data were collected on the Four-Circle diffractometer (FCD) at HANARO in Korea Atomic Energy Research Institute and X-ray date were given by Prof. Y. Noda of Tohoku University Japan. The structure was refined by full-matrix least-square to final R value of 0.070 for 1450 observed reflections by X-ray diffraction and to final R=0.049 for 745 observed reflections by neutron diffraction. With X-ray data we obtained only one hydrogen atomic position. However, not only all atomic positions of four hydrogen atoms at $NH_4$ but also the occupation factors of D and H were refined with neutron data. From this results we obtained the average chemical structure of this sample, $LiND_{3.05}H_{0.95}SO_4$.

• Journal of Applied Reliability
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• v.10 no.1
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• pp.57-64
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• 2010

The HANARO nuclear research reactor had been operated successfully and smoothly up to the year 2008 since its first year of instability in year 1995 just after the completion of construction. But the reliability of the reactor has been degraded from the year 2009 due to new experimental facilities such as Feul Test Loop(FTL) and Cold Neutron Source(CNS) which were installed in the HANARO plant. It turned out that these new facilities contributed unexpected stoppage of the plant. This paper describes causes of stoppage and suggestions to improve the reliability of the plant.

• Journal of Radiation Protection and Research
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• v.39 no.2
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• pp.109-117
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• 2014

Nuclear emergency planning is to plan sheltering, evacuation and iodine prophylaxis for the residents living in the area where the emergency plan is needed, the area is confirmed based on the dose assessment using the source-term through an accident analysis and the data measured from meteorological tower. In this study, the does change before and after protective measures was assessed stochastically based on the one year meteorological data in the condition of the maximum hypothetical accident which can be considered at the research reactor 'HANARO', and the optimized protective measures were derived based on the reference levels defined as a residual dose by ICRP 2007 recommendation which can be applied in a emergency exposure situation. The optimized protective measures for the HANARO in the maximum hypothetical accident were the evacuation to radius 300 m, the sheltering from 300 m to 800 m, the iodine prophylaxis only for the emergency workers under the protective measures for non emergency workers.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.168-171
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• 2003

The IMEF(Irradiated Materials Examination Facility), located in KAERI site, is a hot cell facility to test and evaluate the irradiation defects or embrittlement through post-irradiation examination(PIEs) of irradiated nuclear fuels and structural materials which are come from HANARO research reactor and commercial nuclear power plants. Therefore, to carry out its own function, the high level solid radioactive wastes, produced through PIEs, are periodically carried out and managed from hot cell to monolith. So far, approximately 30 drums which contains 50 liters are transported to monolith, and it is shown that the quantity is slowly increasing, In this paper, the procedures and work contents of the high level solid radwaste carrying out and management for IMEF are described in detail.

• CORROSION AND PROTECTION
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• v.12 no.1
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• pp.24-29
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• 2013

원자력 발전소의 설계 수명이 늘어나고 기존의 가동 원전 또한 장기 운전을 목표로함에 따라, 원자로 압력용기, 가압기, 증기발생기, 배관 등의 주요 구조재료의 장기 열화에 따른 재료 건전성을 유지하는 것이 매우 중요하다. 특히, 응력부식균열 현상은 장기 열화에 의해 일어날수 있는 구조재료에서의 심각한 취화 문제들중의 하나로써, 이 현상을 예방하거나 지연시키기 위해서는 현상의 근본원인과 작동기구를 규명하는 것은 원전의 안전성 유지를 위해 매우 중요하다. 이를 위해서 구조재료 표면의 원전 운전 조건에서의 산화막 특성과 그 형성 거동을 분석하는 것은 매우 중요하게 되는데, 원전 운전 조건은 고온고압의 수화학 환경으로 일반 환경에서 사용가능한 다양한 분석 방법들을 적용하기에 많은 제약을 받게 된다. 그러나, 라만 분광법은 가동 원전의 운전 조건인 고온/고압수 환경 하에서도 실시간으로 산화막 분석이 가능한 기법으로, 본 논문에서는 지금까지의 라만 분광법을 이용하여 고온고압수 환경에서의 주요 구조용 금속 및 합금 표면에 생성된 산화막에 대한 분석 연구 결과에 대하여 소개하고, 앞으로 이를 이용한 구조재료의 열화 현상을 분석 및 열화기구 규명을 위한 연구개발 방향을 제시하고자 한다.

• Progress in Medical Physics
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• v.18 no.2
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• pp.87-92
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• 2007

A thermal neutron beam facility utilizing a typical tangential beam port for Neutron Capture Therapy was installed at the HANARO, 30 MW multi-purpose research reactor. Mixed beams with different physical characteristics and relative biological effectiveness would be emitted from the BNCT irradiation facility, so a quantitative analysis of each component of the mixed beams should be performed to determine the accurate delivered dose. Thus, various techniques were applied including the use of activation foils, TLDs and ionization chambers. All the dose measurements were perform ed with the water phantom filled with distilled water. The results of the measurement were compared with MCNP4B calculation. The thermal neutron fluxes were $1.02E9n/cm^2{\cdot}s\;and\;6.07E8n/cm^2{\cdot}s$ at 10 and 20 mm depth respectively, and the fast neutron dose rate was insignificant as 0.11 Gy/hr at 10 mm depth in water The gamma-ray dose rate was 5.10 Gy/hr at 20 mm depth in water Good agreement within 5%, has been obtained between the measured dose and the calculated dose using MCNP for neutron and gamma component and discrepancy with 14% for fast neutron flux Considering the difficulty of neutron detection, the current study support the reliability of these results and confirmed the suitability of the thermal neutron beam as a dosimetric data for BNCT clinical trials.

• Bulletin of the Korean Space Science Society
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• 2003.10a
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• pp.60-60
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• 2003

과학위성 1호에는 원자외선 분광기를 포함한 다섯 개의 탑재체가 있다. MMS(Mass Memory System)는 이들 탑재체가 수집한 데이터를 대용량 메모리에 저장한 후 지상국으로 보내는 역할을 하며 우주방사선에 의한 메모리 데이터의 오류와 무선 채널을 통한 Downlink 상에서 발생하는 오류를 최소화하기 위해서 소프트웨어적으로 에러를 정정할 수 있는 Reed-Solomon Code를 사용 하였다. 탑재체의 데이터를 저장하기 위한 대용량 메모리는 총 2Gbits로써 8M SRAM, 64M SDRAM, 256M SDRAM의 세 가지로 구성되어 있으며 메모리 여러 개를 하나의 모듈로 만들고 이 모듈이 층으로 쌓여서 MMS에 탑재되어 있다. SRAM에 비해서 집적도가 매우 높은 SDRAM은 공간을 적게 차지하는 장점은 있지만 우주용이 아니므로 그 안정성을 보장할 수 없으므로 우리별 3호에서 성능이 입증된 SRAM과 같이 탑재되었다. 본 연구에서는 MMS의 구조, 동작모드, Spec 및 연구 개발 내용을 소개한다.

• Journal of the Korean Society of Safety
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• v.13 no.4
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• pp.286-291
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• 1998

This paper includes discussion on developing the test verified finite element model for one of the seismic qualification(safety) approaches. It presents a test verified finite element model of a UPS(Uninterruptible Power Supply System) to be used at KMRR, KAERI. The test verified model predicts natural frequencies within 5 percent error for all major modes below 50Hz. This model accurately represents the dynamic characteristics of the actual hardware and is qualified for its use in the final stress analysis for seismic verification.