• Proceedings of the KIEE Conference
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• 2015.07a
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• pp.1565-1566
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• 2015

As a result of increasing power demand and concern about power supply shortage in the world, various energy sources without depletion of fossil fuel are installed to electrical network. Above all, nuclear energy can be considered as the most economical energy source to generate electricity. But recently, due to problem of safety which has emerged as a key social issue, additional construction of nuclear power plants is difficult. In order to replace nuclear power, researches on the emergency generator have been actively conducting. This study conducted a survey of public institutions about specification of backup generator system and current states to secure available capacity.

• Proceedings of the KIEE Conference
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• 2015.07a
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• pp.689-690
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• 2015

국내 최초 원전인 고리1호기는 지난 2007년 30년의 운전수명을 마친 뒤 정부의 안전점검을 거쳐 10년간 연장운전에 들어갔다. 이 과정에서 원전의 비상 전원 계통 신뢰성 확보를 위해 설계수명을 초과한 35년 된 노후 비상디젤발전기(Emergency Diesel Generator, 이하 EDG)를 지난 2013년 4월부터 9월까지 약 6개월에 걸쳐 교체하게 되었으며, 국내 원전 EDG 총 42대 중 18대가 20년 넘게 운영되고 있고, 2025년까지 고리 1호기를 후속으로 월성1호기, 고리2호기, 고리3호기, 고리4호기, 한빛1호기 순으로 40년 승인된 운전 인허가 기간이 만료된다.[1]. 본 연구에서, Class 1E EDG 교체 시 신규 EDG 설계기준, 용량결정, 해석 및 평가에 대한 기술적 방법들을 고리1호기의 사례를 통해 고찰하였다.

• Journal of Fisheries and Marine Sciences Education
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• v.29 no.3
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• pp.920-931
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• 2017

Since the export of Korean-type APR 1400 in 2009 to the UAE, Korea has been achieved management performance, quality inspections, training, nuclear fuel exports for the nuclear power plant. Despite this apparent growth, there are lacking of the research on the marine transportation of radioactive waste. And the terrible accident at the Japan nuclear power plant in 2011 has caused another reconsideration such as emergency response training and plan, reinforcement of safety regulation. According to the Korean government aims to rebuild the appropriate regulation, training, education that is necessary in order to ensure the safety of marine transportation of radioactive waste. Therefore, this study analyzed the various problems identified by the team of experts for the radioactive waste and marine field, the investigation of relevant legal basis, the need for emergency response training for the person in charge of radioactive waste and suggested the simulation-based interactive curriculum during the process of safety verification related to the marine transport of mid- and low-level radioactive waste generated at the Yeon-ggwang nuclear power(Hanbit) plant in 2015.

• Nuclear Engineering and Technology
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• v.55 no.12
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• pp.4576-4582
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• 2023

The Korea retrospective dosimetry (KREDOS)-electron paramagnetic resonance (EPR) group undertook an intercomparison investigation utilizing hydroxyapatite. This analysis involved four institutions: the Korea Institute of Radiological and Medical Sciences, Dongnam Institute of Radiological and Medical Sciences, Korean Association for Radiation Application, and Radiation Health Institute of Korea Hydro & Nuclear Power. Following the irradiation of the hydroxyapatite sample, the recorded build-up was analyzed. To validate the reliability of the EPR dosimetry findings and enhance its operational performance, a hydroxyapatite dose-response curve was plotted and dosimetry was performed for a blind sample. The proficiency of each laboratory was assessed by employing an interlaboratory comparison methodology. This involved a comparative analysis of the measurement results by calculating the relative bias, z-score, and En value. The results submitted by the participating laboratories demonstrated satisfactory ratings for doses of 1.006, 3.999, and 6.993 Gy. Following the second intercomparison, efforts to optimize their hydroxyapatite-EPR dosimetry systems are underway in the participating laboratories. The current assessment of hydroxyapatite dose yielded the foundational data required to establish the parameters of dental dosimetry. In future, the third intercomparison experiment will be conducted for exploring other materials.

• Nuclear Engineering and Technology
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• v.37 no.5
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• pp.491-502
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• 2005

Reliable human performance is a prerequisite in securing the safety of complicated process systems such as nuclear power plants. However, the amount of available knowledge that can explain why operators deviate from an expected performance level is so small because of the infrequency of real accidents. Therefore, in this study, a database that contains a set of useful information extracted from simulated emergencies was developed in order to provide important clues for understanding the change of operators' performance under stressful conditions (i.e., real accidents). The database was developed under Microsoft Windows TM environment using Microsoft Access $97^{TM}$ and Microsoft Visual Basic $6.0^{TM}$. In the database, operators' performance data obtained from the analysis of over 100 audio-visual records for simulated emergencies were stored using twenty kinds of distinctive data fields. A total of ten kinds of operators' performance data are available from the developed database. Although it is still difficult to predict operators' performance under stressful conditions based on the results of simulated emergencies, simulation studies remain the most feasible way to scrutinize performance. Accordingly, it is expected that the performance data of this study will provide a concrete foundation for understanding the change of operators' performance in emergency situations.

• Nuclear Engineering and Technology
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• v.49 no.5
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• pp.979-988
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• 2017

The feasibility of cooling in a pressurized heavy water reactor after a large break loss-of-coolant accident has been analyzed using Multidimensional Analysis of Reactor Safety-KINS Standard code during the recirculation phase. Through evaluation of sensitivity of the fuel channel temperature to various effective recirculation flow areas, it is determined that proper cooling of the fuel channels in the broken loop is feasible if the effective flow area remains above approximately 70% of the nominal flow area. When the flow area is reduced by more than approximately 25% of the nominal value, however, incipience of boiling is expected, after which the thermal integrity of the fuel channel can be threatened. In addition, if a dramatic reduction of the recirculation flow occurs, excursions and frequent fluctuations of temperature in the fuel channels are likely to be unavoidable, and thus damage to the fuel channels would be anticipated. To resolve this, emergency coolant supply through the newly installed external injection path can be used as one alternative means of cooling, enabling fuel channel integrity to be maintained and permanently preventing severe accident conditions. Thus, the external injection flow required to guarantee fuel channel coolability has been estimated.

• Korean Security Journal
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• no.53
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• pp.255-279
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• 2017

The development of North Korea's nuclear weapons has worsened to the sixth nuclear test in 2017, and despite the sanctions of the international community including our government, we have not been able to offer clear solutions and alternatives, and the current measures are not enough in case of North Korea is using nuclear weapons. This study suggests how we should be prepared against the use of nuclear weapons under the premise that North Korea will never give up development of nuclear weapons under any circumstances. The first chapter outlines the current status of our preparedness if North Korea makes a nuclear attack. The second chapter analyzes and evaluates the power of nuclear weapons and North Korea's nuclear weapons threat. In the third chapter, we analyze North Korea nuclear attack and analyze the wartime emergency situation and civil defense posture. Finally, in order to implement the solutions presented in the text, we will identify priorities and summarize further developments.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2005.06a
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• pp.496-512
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• 2005

It is internationally proposed that generic intervention levels (GILs) and generic action levels, determined based on cost-benefit analyses, be used as the decision criteria for public protective actions in a nuclear emergency. Operational intervention levels (OILs) are directly or easily measurable quantities corresponding to these generic levels. To assess the necessity of protective actions in a nuclear emergency, it is important that the environmental monitoring data required for applying and revising OILs should be promptly produced. It is discussed what and how to do for this task in the course of emergency response and preparedness.

• Nuclear Engineering and Technology
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• v.55 no.1
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• pp.295-303
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• 2023

Whole-body counters are widely used to assess internal contamination after a nuclear accident. However, it is difficult to determine radioiodine activity due to limitations in conventional calibration phantoms. Inhaled or ingested radioiodine is heterogeneously distributed in the human body, necessitating time-dependent biodistribution for the assessment of the internal contamination caused by the radioiodine intake. This study aims at calculating counting efficiencies considering the biodistribution of ¹³¹I in whole-body counting measurement. Monte Carlo simulations with computational human phantoms were performed to calculate the whole-body counting efficiency for a realistic radioiodine distribution after its intake. The biodistributions of ¹³¹I for different age groups were computed based on biokinetic models and applied to age- and gender-specific computational phantoms to estimate counting efficiency. After calculating the whole-body counting efficiencies, the efficiency correction factors were derived as the ratio of the counting efficiencies obtained by considering a heterogeneous biodistribution of ¹³¹I over time to those obtained using the BOMAB phantom assuming a homogeneous distribution. Based on the correction factors, the internal contamination caused by ¹³¹I can be assessed using whole-body counters. These correction factors can minimize the influence of the biodistribution of ¹³¹I in whole-body counting measurement and improve the accuracy of internal dose assessment.

• Proceedings of the KIEE Conference
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• 2009.07a
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• pp.666_667
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• 2009

원자력발전소의 비상전력계통은 소외정전 시 발전소 안전정지에 필요한 안전관리 설비에 비상전력을 공급하는 계통으로 비상전력계통 모선에 비상디젤발전기(Emergency Diesel Generator : EDG)가 설치되어 있다. 본 논문에서는 국내 중수로형 원자력 발전소에 대해서 최초로 주기적 안전성 평가(Periodic Safety Review : PSR)을 수행한 결과를 기술하였다.