• Journal of radiological science and technology
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• v.29 no.1
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• pp.39-46
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• 2006

The rules and terms are described different meaning, in this results the research is accomplished for preventing practical workers from confusion. Atomic law are kept up modification and development in our situation by the ICRP's recommendation, on the other hand, the rules of diagnosis radiation equipment safety managements are modified partial, then resulted in confusion. The study was comparison between the rules of diagnosis radiation equipment safety management and atomic energy law, and the modification items obtained were as follows. 1. With each other different the terms and units are used. With the exception of special terms for affairs usage, it is needless to say that common term uniformity is standardized. The standardization of rules and guidance have not need to confusion radiological practical workers. 2. The following is omitted. 1) The radiation protection against tile patient and the hospital visitor. 2) Radiation dose limit of the woman patient who is in the process of becoming pregnant. 3) Radiation dose limit of the person who is not regarded as madical madical exposure. 4) The control of the exposure of pregnant of women at work.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2014.10a
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• pp.102-105
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• 2014

In accordance with U.S. Nuclear Regulatory Commission regulatory guide(NRC RG) 1.20(Rev.3), we are writing a comprehensive vibration assessment program(CVAP) design control document(DCD) and a technical report for U.S. NRC design certification(DC) of an Advanced Power Reactor 1400(APR1400) nuclear power plant(NPP). CVAP of an APR1400 NPP for U.S. NRC DC is classified as a non-prototype category 1 type. Therefore, CVAP DCD of reactor vessel internals(RVI) and steam generator internals(SGI) consist of analysis and full inspection program. However, piping system of primary and secondary system will be described as measurement program.

• The Science & Technology
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• v.10 no.3 s.94
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• pp.16-19
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• 1977

1946년 그러니까 제2차 세계대전이 끝난 이듬해었다. 미국 메리랜드주의 수도이며 주의회가 위치한 에너폴리스의 해군사관학교를 졸업하게 된 한 젊은 이학사(BACHELOR OF SCIENCE)인 그는 수학, 이학, 공학에 정통한 유망한 사관으로서 승선하게 되었다. 전자공학과 사진담당 사관이었던 그는 "해중에서 전파의 전파"에 관한 논문을 쓴바 있다. 죠지아주 땅콩농장에 돌아가기 일년전 원자력대체수반의 승조사관에 임명되어 수학, 물리를 강의도 했고 원자로의 해체도 훌륭히 수행한바 있다. 미국과학기술계에서는 과학과 기술에 상당한 지식을 갖고 있는 대통령으로서 미국역사상 허벋, 후버이래에 이공계출신 대통령이라느니 Fourier급수로 부터 Bessel함수까지 통달하고 있는 대통령이니 하며 기대를 걸고 있다. 카터씨가 죠지아주지사로 있을때 과학제문을 두고 과학기술고문위원회를 열었으며, 주청은 죠지아대학의 성과를 이용하고 있는가? NASA의 자원위성을 죠지아주 지도제작에 이용할 수 없겠는가? 수질오염방지, 농업재해예방 씨스템 등을 검토했다. 개인적으로도 땅콩밭의 경영자로서 땅콩의 성숙기와 추수시기에 관한 연구가이기도 했다. 카터는 자유주의 개혁자로도 알려지고 있으며 환경보존에도 단호히 임하고 있다.

• 전기의세계
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• v.46 no.12
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• pp.18-22
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• 1997

우리 학회에서는 선진국과의 기술협력 강화, 국제적 입지의 향상, 국내 연구의 활성화 등의 취지로 1994년부터 ISAP 국제학술회의의 국내 유치를 추진하였으며 노력을 경주한 결과 1995년 12월 ISAP 국제운영위원회(ISC:International Steering Committee)로부터 유치 확정 통보를 받았다. 1996년 1월에 본 학회 이사회에서는 ISP'97 국제 학술회의를 학회 창립 50주년 기념행사의 일환으로 치를 것을 결정하였고 1996년 2월 ISAP'96 대회기간중 열린 ISC 회의에서 원래 '97년 8월중으로 예정된 개최일자를 '97년 7월로의 변경을 신청하여 승인하였다. ISP'97 국제학술회의에서는 창립 50주년 기념 국제학술회의로서의 의의를 높이고 많은 회원들의 참여를 유도하기 위하여 대회 주제의 범위를 전력시스템 분야만이 아니고 발전소, 전기기기, 원자력 등을 포함한 일반 전기공학의 모든 분야에 있어서의 지능형시스템 신기술 응용으로 확대하였다.

• Journal of Radiation Protection and Research
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• v.37 no.3
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• pp.116-122
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• 2012

A short-term atmospheric dispersion factor (${\chi}/Q$) is an essential element for radiological dose assessment following a hypothetical accidental releases of light-water nuclear power plants. The U. S. NRC developed PAVAN program to comply with the U. S. NRC's Regulatory Guide 1.145. Meteorological data is an essential element for atmospheric dispersion, and PAVAN uses a joint frequency distribution data, which represents the occurrence probability of wind speed and wind direction for atmospheric stability. Using the meteorological data measured at Kori and Wolsung sites for the last 5 years (from 2006 to 2010), a variety of joint frequency distribution data were prepared to evaluate ${\chi}/Q$ values with different wind speed classifications (U. S. NRC's recommendation and even distribution of occurrence probability) and periods of meteorological data to be analyzed (1 year, 2 year, 3 year, 4 year, 5 year). As a result, it was found that the influence of the wind speed classification on ${\chi}/Q$ values is little, while the influence of the periods of meteorological data to be analyzed is relatively significant, representing more than 1.5 times in the ratio of maximum to minimum values.

• Journal of the Korean Society of Radiology
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• v.17 no.2
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• pp.267-275
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• 2023

Occupational exposure records are subject of global interest, and analysis of radiation workers in work categories is being conducted. In Rep. of Korea, according to relevant ministries, the MOHW(Ministry of Health and Welfare), the MAFRA(Ministry of Agriculture, Food and Rural Affairs), and the NSSC(Nuclear Safety and Security Commission) collect and analyze records of occupational exposure by dividing them into 11 work categories. However, this classification system lacks consistency with the systems of major countries, including the UNSCEAR(United Nations Scientific Committee on the Effects of Atomic Radiation). The domestic radiation work field classification system does not have clear classification criteria and does not reflect the characteristics of the radiation work field. Through the analysis of the classification system of the UNSCEAR, we suggested the five main categories(nuclear cycle, medical, industrial, others(education/research, military/public) field and several sub-categories according to each radiation work field.

• Journal of Radiation Protection and Research
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• v.38 no.2
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• pp.60-67
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• 2013

A diffusion coefficient is an important parameter in the prediction of atmospheric dispersion using a Gaussian plume model, and its modelling approach varies. In this study, dispersion coefficients recommended by the U. S. Nuclear Regulatory Commission's (U. S. NRC's) regulatory guide and the Canadian Nuclear Safety Commission's (CNSC's) regulatory guide, and used in probabilistic accident consequence analysis codes MACCS and MACCS2 have been investigated. Based on the atmospheric dispersion model for a hypothetical accidental release recommended by the U. S. NRC, its influence to atmospheric dispersion factor was discussed. It was found that diffusion coefficients are basically predicted from a Pasquill- Gifford curve, but various curve fitting equations are recommended or used. A lateral dispersion coefficient is corrected with consideration for the additional spread due to plume meandering in all models, however its modelling approach showed a distinctive difference. Moreover, a vertical dispersion coefficient is corrected with consideration for the additional plume spread due to surface roughness in all models, except for the U. S. NRC's recommendation. For a specified surface roughness, the atmospheric dispersion factors showed differences up to approximately 4 times depending on the modelling approach of a dispersion coefficient. For the same model, the atmospheric dispersion factors showed differences by 2 to 3 times depending on surface roughness.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.13 no.1
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• pp.45-53
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• 2015

Since the commercial operation of Kori Unit #1 nuclear power plant(NPP) started in 1978, 23 units at present are operating in Korea. Radioactive wastes will be steadily generated from these units and accumulated. In addition, the life-extension of NPPs, construction of new NPPs and decontamination and decommissioning research facilities will cause radioactive wastes to increase. Recently, Korea has revised the new classification criteria as was proposed by IAEA. According to the revised classification criteria, low-level, very-low-level and exempt waste are estimated to about 98% of total disposal amount. In this paper, current status of overseas cases and disposal method with new classification criteria are analyzed to propose the most reasonable method for estimating the amount of decommissioning waste when applying the new criteria.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.12 no.4
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• pp.299-314
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• 2014

A lifting device is used to deal with transport cask for the transportation of spent fuels from nuclear power plants. This study performed theoretical analysis and numerical simulation to evaluate the structural integrity of the lifting device based on Nuclear Safety and Security Commission(NSSC) Notice No.2013-27 and US 10CFR Part 71 ${\S}71.45$. The results of theoretical analysis showed that the maximum stresses of all components were below the allowable values. This result confirmed that the lifting device was structurally safe during operation. The results of finite element analysis also showed that it was evaluated to satisfy the design criteria bothyielding and ultimate condition. All components have been shown to ensure the structural safety due to sufficient safety margins. In other words, the safety factor was 3 or more for the yielding condition and was 5 or more for the ultimate condition.

• Nuclear Engineering and Technology
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• v.26 no.3
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• pp.355-366
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• 1994

The USNRC issued a revised ECCS rule that allows the use of best estimate computer codes for safety analysis. The rule also requires an estimation of uncertainty in calculated system response when applying the best estimate computer codes. A practical realistic evaluation methodology to evaluate the ECCS performance that satisfies the requirements of the ECCS rule has been developed and this paper describes the application of new realistic evaluation methodology to large break LOCA for, the demonstration of the new methodology. The computer code RELAP5/MOD3/KAERI, which was improved from RELAP5/MOD3.1, was used as the best estimate code in the application. The uncertainty of the code was evaluated by assessing several separate and integral effect tests, and for the application to actual plant Kori 3 & 4 was selected as the reference plant. Response surfaces for blowdown and reflood PCTs were generated from the results of the sensitivity analyses and probability distribution functions were established by random sampling or Monte-Carlo method for each response surface. Final uncertainties were quantified at 95% probability level and safety margins for large break LOCA were discussed.