• Proceedings of the Korean Radioactive Waste Society Conference
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• 2019.05a
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• pp.114-115
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• 2019

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.19 no.1
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• pp.141-160
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• 2021

Unit 1 of the Kori Nuclear Power Plant (NPP) and Unit 1 of the Wolsong NPP are being prepared for decommissioning; their decommissioning is expected to generate large amounts of intermediate-level, low-level, and very low level Waste. Mixed waste containing both radioactive and hazardous substances is expected to be produced. Nevertheless, laws and regulations, such as the Korean Nuclear Safety Act and Waste Management Act, do not define clear regulatory guidelines for mixed waste. However, the United States has strictly enforced regulations on mixed waste, focusing on the human health and environmental effects of its hazardous components. The U.S. Nuclear Regulatory Commission and the U.S. Department of Energy regulate the radioactive components of mixed waste under the Atomic Energy Act. The U.S. Environmental Protection Agency regulates the hazardous waste component of mixed waste under the Resource Conservation and Recovery Act. In this study, the laws, regulations, and authorities pertaining to mixed waste in the United States are reviewed. Through comparison and analysis with waste management laws and regulations in Korea, a treatment direction for mixed waste is suggested. Such a treatment for mixed waste will increase the efficiency of managing mixed waste when decommissioning NPPs in the near future.

• Proceedings of the Korean Nuclear Society Conference
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• 2004.10a
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• pp.1119-1120
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• 2004

• Proceedings of the Korean Nuclear Society Conference
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• 2005.05a
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• pp.265-266
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• 2005

• Proceedings of the Korean Nuclear Society Conference
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• 2003.10a
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• pp.504.2-504.2
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• 2003

• Fire Science and Engineering
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• v.24 no.4
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• pp.116-122
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• 2010

The fire protection system of nuclear power plants shall be designed, constructed and operated, through a defense-in depth criterion to suppress the leakage of radioactivity to the outside and to allow the safety shutdown function when a fire occurs. In order to achieve these purposes, most of countries abroad operating the nuclear power plants keep up the integrated regulations, however we have two guidelines, the fire protection service act and the nuclear energy act, as mandatory requirements to apply to the fire protection systems in nuclear power plants. It has shown that USA, Canada and Japan which have long experience in operating nuclear power plants have regulations integrated technically for fire protection system of nuclear power plants. It is proposed that the things once verified the risk analysis of the fire hazard by the nuclear law in the design for fire suppression system in plants should be authorized by the fire protection service act as an exception.

• Journal of Digital Convergence
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• v.17 no.8
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• pp.47-60
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• 2019

The purpose of this study is to explore the overall structural relationship between the statutory provisions of nuclear energy legislation and to identify the coherence of the nuclear law system using social network analysis. In particular, we analyze the legal structure of the "Nuclear Safety Act", which plays a central role in nuclear safety regulation, to examine the key provisions in legal network structure of Nuclear Safety Act. Therefore, we found the structural problems of the nuclear legal system and suggest the legislative improvement plan for reducing excessive legislative activity and determining the need for legal amendments in nuclear safety management and regulation. This study is expected to provide a analytical framework for making legal system of further policy in other science and technology industries as well as nuclear energy related industries.

• Journal of Korean Society of Industrial and Systems Engineering
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• v.34 no.3
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• pp.79-89
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• 2011

Since commercial operation of Kori-1 nuclear power plant in 1978, twenty units are under operation and six units are under construction at 2011 present. Nuclear power become a main energy source in our country. However, the plant was constructed by a USA vendor in its beginning period, the Quality Assurance requirements of USA was applied. Even though Quality Assurance requirements were newly established to the Korea Atomic Energy Act, its contents are quite similar to those of USA. And 10 CFR 50 App.B, ASME NQA-1 apply to most of nuclear industries as a quality assurance plan. In this paper, Quality Assurance requirement of domestic nuclear industries has been investigated and applicable method of ISO Quality Assurance application to the nuclear industries is suggested by a comparison ISO 9000 and nuclear quality assurance specification.

• Journal of Radiation Protection and Research
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• v.28 no.4
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• pp.281-290
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• 2003

The KN-12 spent nuclear fuel transport cask, which is a Type B(U) package designed to comply with the requirements of Korea Atomic Energy Act[1], IAEA Safety Standards Series No.TS-R-1[2] and US 10 CFR Part 71[3], is designed for carrying up to 12 PWR spent fuel assemblies in a basket structure. The cask has been licensed in accordance with Korea Atomic Energy Act and was fabricated in Korea in accordance with the requirements of ASME B&PV Sec.III, Div.3[4]. The cask must maintain thermal integrity in accordance with the related regulations and be evaluated to verify that the thermal performance of the cask complies with the regulatory requirements. The temperatures of the cask and components were determined by using finite elements methods with a numerical tool, safety tests using an 1/8 height slice model of the real cask were conducted to demonstrate verification of the numerical tool and methods, and heat transfer tests for normal transport conditions were performed as a fabrication acceptance test to demonstrate the heat transfer capability of the cask.

• Journal of radiological science and technology
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• v.43 no.6
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• pp.481-487
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• 2020

Radiation measurement technology has steadily improved and its usage is expanding in various industries such as nuclear medicine, security search, satellite, nondestructive testing, environmental industries and the domain of nuclear power plants (NPPs). Especially, the simultaneous measurements of gamma rays and neutrons can be even more critical for nuclear safety management of spent nuclear fuel and monitoring of the nuclear material. A semiconductor detector comprising cadmium, zinc, and tellurium (CZT) enables to detect gamma-rays due to the significant atomic weight of the elements via immediate neutron and gamma-ray detection. Semiconductor sensors might be used for nuclear safety management by monitoring nuclear materials and spent nuclear fuel with high spatial resolution as well as providing real-time measurements. We aim to introduce a portable nuclide-analysis device that enables the simultaneous measurements of neutrons and gamma rays using a CZT sensor. The detector has a high density and wide energy band gap, and thus exhibits highly sensitive physical characteristics and characteristics are required for performing neutron and gamma-ray detection. Portable nuclide-analysis device is used on NPP-decommissioning sites or the purpose of nuclear nonproliferation, it will rapidly detect the nuclear material and provide radioactive-material information. Eventually, portable nuclide-analysis device can reduce measurement time and economic costs by providing a basis for rational decision making.