• Nuclear Engineering and Technology
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• 제55권2호
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• pp.696-706
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• 2023

Consequences of an anticipated Beyond Design Basis Accident (BDBA) Long-Term Station Blackout (LTSBO) event with complete loss of grid power in the VVER-1200 reactor of Rooppur Nuclear Power Plant (NPP) of Unit-1 are assessed using the RASCAL 4.3 code. This study estimated the released radionuclides, received public radiological dose, and ground surface concentration considering 3 accident scenarios of International Nuclear and Radiological Event Scale (INES) level 7 and two meteorological conditions. Atmospheric transport, dispersion, and deposition processes of released radionuclides are simulated using a straight-line trajectory Gaussian plume model for short distances and a Gaussian puff model for long distances. Total Effective Dose Equivalent (TEDE) to the public within 40 km and radionuclides contribution for three-dose pathways of inhalation, cloudshine, and groundshine owing to airborne releases are evaluated considering with and without passive safety Emergency Core Cooling System (ECCS) in dry (winter) and wet (monsoon) seasons. Source term and their release rates are varied with the functional duration of passive safety ECCS. In three accident scenarios, the TEDE of 10 mSv and above are confined to 8 km and 2 km for the wet and dry seasons, respectively in the downwind direction. The groundshine dose is the most dominating in the wet season while the inhalation dose is in the dry season. Total received doses and surface concentration in the wet season near the plant are higher than those in the dry season due to the deposition effect of rain on the radioactive substances.

• 한국화재소방학회논문지
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• 제30권4호
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• pp.20-26
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• 2016

원자력발전소의 화재방호 목적은 예방, 화재의 진압 및 영향을 완화하는 데 있으며, 화재가 발생하면 원자로를 안전하게 정지하여 유지하고 환경으로 방사성물질의 유출을 최소화하는 것이다. 미국의 원자력규제위원회는 10CFR50.48과 10CFR50 APP.R을 발행한 이래 지난 20여년간 화재방호와 관련하여 많은 일반 통신문(Generic Communications)을 발행하였으며, 미국원전 발전사업자(Nuclear Energy Institute)에서는 회로고장 해결을 위한 다중오동작과 관련된 결정론적 방법 등을 사용과 연계하여 위험도정보를 활용한 화재 안전정지분석 방법론을 개발하였다. 본 논문에서는 중수로원전의 주제어실 화재시 화재안전정지분석 방법론을 적용하여 안전정지용 한 계열의 안전관련 계통 및 기기가 손상되어도 원자로의 사고 후 안전정지를 달성하고 유지함을 확인하였다.

• Nuclear Engineering and Technology
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• 제46권6호
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• pp.803-816
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• 2014

Defense-in-depth is a fundamental safety principle for the design and operation of nuclear power plants. Despite its general appeal, defense-in-depth is not without its drawbacks, which include its potential for concealing the occurrence of hazardous states in a system, and more generally rendering the latter more opaque for its operators and managers, thus resulting in safety blind spots. This in turn translates into a shrinking of the time window available for operators to identify an unfolding hazardous condition or situation and intervene to abate it. To prevent this drawback from materializing, we propose in this work a novel safety principle termed "observability-in-depth". We characterize it as the set of provisions technical, operational, and organizational designed to enable the monitoring and identification of emerging hazardous conditions and accident pathogens in real-time and over different time-scales. Observability-in-depth also requires the monitoring of conditions of all safety barriers that implement defense-in-depth; and in so doing it supports sensemaking of identified hazardous conditions, and the understanding of potential accident sequences that might follow (how they can propagate). Observability-in-depth is thus an information-centric principle, and its importance in accident prevention is in the value of the information it provides and actions or safety interventions it spurs. We examine several "event reports" from the U.S. Nuclear Regulatory Commission database, which illustrate specific instances of violation of the observability-in-depth safety principle and the consequences that followed (e.g., unmonitored releases and loss of containments). We also revisit the Three Mile Island accident in light of the proposed principle, and identify causes and consequences of the lack of observability-in-depth related to this accident sequence. We illustrate both the benefits of adopting the observability-in-depth safety principle and the adverse consequences when this principle is violated or not implemented. This work constitutes a first step in the development of the observability-in-depth safety principle, and we hope this effort invites other researchers and safety professionals to further explore and develop this principle and its implementation.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.424-435
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• 2016

Background: The International Commission on Radiological Protection (ICRP) recommendations and the Federal Guidance Report (FGR) published by the U.S. Environmental Protection Agency (EPA) have been widely applied worldwide in the fields of radiation protection and dose assessment. The dose conversion coefficients of the ICRP and FGR are widely used for assessing exposure doses. However, before the coefficients are used, the user must thoroughly understand the derivation process of the coefficients to ensure that they are used appropriately in the evaluation. Materials and Methods: The ICRP provides recommendations to regulatory and advisory agencies, mainly in the form of guidance on the fundamental principles on which appropriate radiological protection can be based. The FGR provides federal and state agencies with technical information to assist their implementation of radiation protection programs for the U.S. population. The system of radiation dose assessment and dose conversion coefficients in the ICRP and FGR is reviewed in this study. Results and Discussion: A thorough understanding of their background is essential for the proper use of dose conversion coefficients. The FGR dose assessment system was strongly influenced by the ICRP and the U.S. National Council on Radiation Protection and Measurements (NCRP), and is hence consistent with those recommendations. Moreover, the ICRP and FGR both used the scientific data reported by Biological Effects of Ionizing Radiation (BEIR) and United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) as their primary source of information. The difference between the ICRP and FGR lies in the fact that the ICRP utilized information regarding a population of diverse races, whereas the FGR utilized data on the American population, as its goal was to provide guidelines for radiological protection in the US. Conclusion: The contents of this study are expected to be utilized as basic research material in the areas of radiation protection and dose assessment.

• 한국강구조학회 논문집
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• 제22권5호
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• pp.487-496
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• 2010

미국의 NRC(United States Nuclear Regulatory Commission)에서 발간된 "Regulatory Guide 1.61 of United States NRC(2007)"는 원전구조물의 내진설계에 적용되는 구조감쇠비를 철근콘크리트(이하 RC)구조의 경우 4%(OBE)와 7%(SSE), 강구조의 경우 3%(OBE)와 4%(SSE)를 규정하고 있다. 그러나 최근 개발된 강판-콘크리트(이하 SC)구조의 경우 구조감쇠비에 대한 규정이 없다. 본 연구의 목적은 RC구조와 SC구조의 감쇠비의 상대적 차이를 비교함으로서 SC구조의 감쇠비를 조사하는 것이다. 4개의 실험체, RC-S, RC-M, SC-S 그리고 SC-M에 대한 실험적 연구가 수행되었다. 뒷 글자 S와 M은 실험체의 거동이 전단에 의해 지배되는 것과 휨에 의해 지배되는 것을 의미한다. 실험방법은 엑츄에이터와 실험체의 질량사이를 연결하는 인장시험편이 파단되면서 실험체의 자유진동을 발생하게 하는 방법을 적용하였다. 가속도계를 이용하여 측정된 실험데이타를 분석하여 하중의 크기에 따른 기본진동수와 감쇠비를 결정하였다. 4개 실험체의 감쇠비를 비교분석하여 SC구조의 감쇠비는 OBE해석에 RC구조와 동일하게 4%를 제안하였으며 SSE해석의 경우 RC구조의 감쇠비보다 1% 적은 6%를 제안하였다.

• 방사성폐기물학회지
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• 제14권3호
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• pp.267-277
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• 2016

노후 원전 해체의 경우 부지 특성 및 최종 상태 조사 보고서에 해당 부지내 잔존가능성이 있는 방사성 핵종 정보에 대한 내용을 포함하여야 한다. 미국 NRC의 경우 이에 해당하는 해체기술관련문서(DTBD)를 부지 특성 조사시에 부지이력조사(HSA)와 같이 사업자 측이 제출하도록 규제하고 있다. 또한 해체기술관련문서는 방사선학적 부지 조사와 해체완료계획서에 포함되어야 하는 내용으로써 부지 규제 해제와 재이용에 관해서 중요한 자료를 제공한다. 이 논문은 부지 별 잠재적 핵종에 대해 미국 원전의 해체 사례중 부지 특성 및 최종 상태조사 과정에서 결정하는 방법론을 분석하고 2017년 고리 1호기의 영구 운전정지 후 이루어질 해체 과정에 필수적인 규제 지침과 기술적 근거 수립에 도움이 되고자 한다.

• 방사성폐기물학회지
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• 제5권4호
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• pp.297-308
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• 2007

폐액증발기 농축폐액의 폴리머고화를 위하여 붕산 함유 건조분말에 액상규산나트륨을 과립화제로 활용하여 점적 형태로 분사하고 평균 $2{\sim}4mm$ 크기의 과립을 제조하는 농축폐액 과립화 설비를 제작하였다. 또한 폐수지 폴리머 고형화에 대해 미국 원자력규제위원회(NRC)의 인증을 받은 신규 고화기술을 과립화된 농축폐액에 성공적으로 적용하였다. 상기 고화설비는 기계적인 혼합 대신 중력을 이용한 in-situ 고화처리 방식으로 폐기물의 추가적인 부피증가가 없고 폐기물 적재량을 최대화할 수 있다. 생산된 폴리머 고화체의 성능평가를 위해 화재시험, 압축강도시험, 침출 및 침수시험, 방사선조사시험, 열순환시험을 표준시험법에 따라 수행하였다.

• 한국압력기기공학회 논문집
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• 제12권2호
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• pp.58-65
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• 2016

Since, in case of high energy piping, steam jets ejected from the rupture zone may cause damage to nearby structure, it is necessary to design it into consideration of nuclear power plant design. For the existing nuclear power plants, the ANSI / ANS 58.2 technical standard for high-energy pipe rupture was used. However, the US Nuclear Regulatory Commission (USNRC) and academia recently have pointed out the non-conservativeness of existing high energy pipe fracture evaluation methods. Therefore, it is necessary to develop a highly reliable evaluation methodology to evaluate the behavior of steam jet ejected during high energy pipe rupture and the effect of steam jet on peripheral devices and structures. In this study, we develop a method for analyzing the impact load of a jet by high energy pipe rupture, and plan to carry out an experiment to verify the evaluation methodology. In this paper, the basic data required for the design of the jet impact load experiment equipment under construction, 1) the load change according to the jet distance, 2) the load change according to the jet collision angle, 3) the load variation according to structure diameter, and 4) the load variation depending on the jet impact position, are numerically obtained using the developed steam jet analysis technique.

• Nuclear Engineering and Technology
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• 제54권7호
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• pp.2418-2426
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• 2022

The grouping analysis is a method guided by the Korea Radioactive Waste Agency for efficient analysis of radioactive waste for disposal. In this study, experiments to verify the adequacy of grouping analysis were conducted with radioactive soil, concrete, and dry active waste in similar environments. First, analysis results of the major radionuclide concentrations in individual waste samples were reviewed to evaluate whether wastes from similar environments correspond to a single waste stream. As a result, the soil and concrete waste were identified as a single waste stream because the distribution range of radionuclide concentrations was "within a factor of 10", the range that meet the criterion of the U.S. Nuclear Regulatory Commission for a single waste stream. On the other hand, the dry active waste was judged to correspond to distinct waste streams. Second, after analyzing the composite samples prepared by grouping the individual samples, the population means of the values of "composite sample analysis results/individual sample analysis results" were estimated at a 95% confidence level. The results showed that all evaluation values for soil and concrete waste were within the set reference values (0.1-10) when five-package and ten-package grouping analyses were conducted, verifying the adequacy of the grouping analysis.

• Journal of Radiation Protection and Research
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• 제39권2호
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• pp.89-95
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• 2014

원전의 인허가 승인을 위한 사고결말평가에서 경수로는 미국의 규제지침에서 제시한 바와 같이 방사성물질의 지표침적의 고려를 허용하지 않고 있는데 반해 중수로의 규제지침에서는 이의 고려를 허용하고 있다. 이러한 배경에 따라 본 연구에서는 방사성물질의 지표침적에 의한 피폭영향의 민감도를 정량적으로 고찰, 분석하였다. 가상사고 시나리오를 구성하여 Cs-137과 I-131의 환경방출에 따른 총 피폭선량을 평가한 결과, 방사성물질의 지표침적과 이로 인한 공기중 농도의 감손을 고려치 않는 경우에 보다 보수적 결과를 나타냈다. 이는 지표침적에 의한 피폭선량이 총 피폭선량에 미치는 기여는 상대적으로 적은데 비해 지표침적으로 인한 공기중 농도의 감손이 총 피폭선량에 미치는 기여는 상대적으로 크기 때문이다. 대기안정도, 방출기간, 평가거리 등에 따라 차이는 있지만 두 핵종 모두 총 피폭선량에 대해 흡입에 의한 피폭이 90% 이상을 차지했으며, 지표침적에 의한 피폭은 기껏해야 10% 미만을 나타냈다. 지표침적의 고려에 따른 총 피폭선량의 감소는 $^{137}Cs$ 보다는$^{131}I$의 경우에 보다 컸으며, 대기가 안정하고 방출기간이 길수록, 그리고 방출점으로부터 평가지점이 멀수록 감소경향은 보다 뚜렷하게 나타났다.