• Asian Journal of Atmospheric Environment
• /
• 제8권1호
• /
• pp.59-68
• /
• 2014

The Fukushima nuclear accident in 2011 had an extensive impact on the national electricity plans. This paper outlines alternative electricity scenarios that meet the goals of nuclear phase-out and greenhouse gas (GHG) emission reduction. This paper also analyzes the results of each scenario in respect to the electricity mix, GHG emissions, costs and employment effects. The Long-range Energy Alternatives Planning system (LEAP) model was used to simulate the annual electricity demand and supply system from 2011 to 2030. The reference year was 2009. Scenarios are reference (where existing plans are continued), A1, A2, B1, B2, and C2 (where the levels of demand management and nuclear phase-out are different). The share of renewable energy in the electricity mix in 2030 for each scenario will be increased from about 1% in 2009 to 8% in the reference scenario and from 11% to 31% in five alternative scenarios. Total cumulative cost increases up to 14% more than the reference scenario by replacing nuclear power plants with renewable energy in alternative scenarios could be affordable. Deploying enough renewable energy to meet such targets requires a roadmap for electricity price realization, expansion of research, development and deployment for renewable energy technologies, establishment of an organization dedicated to renewable energy, and ambitious targets for renewable energy.

• Nuclear Engineering and Technology
• /
• 제56권7호
• /
• pp.2806-2820
• /
• 2024

Accurate reconstruction of radiation field and path planning are very important for the safety of operators in the process of dismantling nuclear facilities. Based on radial basis function (RBF) interpolation algorithm, this paper discussed the application of inverse multiquadric radial basis Function (IMRBF) interpolation method to the reconstruction of gamma radiation field, and proved the feasibility of reconstructing a radiation field with multiple γ sources. The average relative errors of IMRBF interpolation results were 4.28% and 8.76%, respectively, for the experimental scenarios with single and double gamma sources. After comparing the consistency between the simulated scene and the experimental scene, IMRBF method and Cubic Spline method were respectively used to reconstruct the gamma radiation field by Geant4 simulation data. The results showed that the interpolation accuracy of IMRBF method was superior to that of Cubic Spline method. Further, more RBF interpolation algorithms were used to reconstruct the multi-γ source radiation field, and then the Probabilistic Roadmap (PRM) algorithm was used to optimize the human walking path in the radiation field reconstructed by different interpolation methods. The optimal paths in radiation fields generated by multiple interpolation methods were compared. The results herein contribute to a comprehensive understanding of RBF interpolation methods in reconstructing γ radiation fields and their application in optimizing paths in radiation environments. The insights may provide valuable information for decision-making in radiation protection during the decommissioning of nuclear facilities.

• Nuclear Engineering and Technology
• /
• 제44권8호
• /
• pp.855-870
• /
• 2012

The paper deals with three main topics: a) the definition of System Thermal-Hydraulics (SYS TH), b) a historical outline for SYS TH and, c) the description of elements for reflection when planning research projects or improvement activities, this last topic being the main reason for the paper. Distinctions between basic thermal-hydraulics and computational Fluid-Dynamics (CFD) on the one side and SYS TH on the other side are considered under the first topic; stakeholders in the technology are identified. The proposal of Interim Acceptance Criteria for Emergency Core Cooling Systems in 1971 by US NRC (AEC at the time) is recognized as the starting date or the triggering event for SYS TH (second topic). The complex codes and the main experimental programs (list provided in the paper) constitute the pillars for SYS TH. Caution or warning statements are introduced in advance when discussing the third topic: a single person (or a researcher) has little to no possibility, or capability, of streamlining the forthcoming investments or to propose a roadmap for future activities. Nevertheless, the ambitious attempt to foresee developments in this area has been pursued without constraints connected with the availability of funds and with industrial benefits or interests. Demonstrating the acceptability of current SYS TH limitations and training in the application of those codes are mentioned as the main challenges for forthcoming research activities.

• 방사성폐기물학회지
• /
• 제21권1호
• /
• pp.65-93
• /
• 2023

Several countries have been operating radioactive waste disposal (RWD) programs to construct their own repositories and have used natural analogues (NA) studies directly or indirectly to ensure the reliability of the long-term safety of deep geological disposal (DGD) systems. A DGD system in Korea has been under development, and for this purpose a generic NA study is necessary. The Korea Atomic Energy Research Institute has just launched the first national NA R&D program in Korea to identify the role of NA studies and to support the safety case in the RWD program. In this article, we review some cases of NA studies carried out in advanced countries considering crystalline rocks as candidate host rocks for high-level radioactive waste disposal. We examine the differences among these case studies and their roles in reflecting each country's disposal repository design. The legal basis and roadmap for NA studies in each country are also described. However because the results of this analysis depend upon different environmental conditions, they can be only used as important data for establishing various research strategies to strengthen the NA study environment for domestic disposal system research in Korea.

• 한국수소및신에너지학회논문집
• /
• 제33권6호
• /
• pp.761-768
• /
• 2022

In the hope of realizing carbon neutrality, Korea has established the goal of expanding the supply of hydrogen electric vehicles through a roadmap to revitalize the hydrogen economy. A prerequisite for successful supply expansion is securing the safety of hydrogen electric vehicles. Certain parts, such as the hydrogen transport pipe and tank, in hydrogen electric vehicles are exposed to high-pressure hydrogen gas over long periods of time, so the hydrogen enters the grain boundary of material, resulting in a degradation of the parts referred to as hydrogen embrittlement. In addition, since the safety of parts utilizing hydrogen varies depending on the type of material used and its environmental characteristics, the necessity for the enactment of a hydrogen embrittlement regulation has emerged and is still being discussed as a Global Technical Regulation (GTR). In this paper, we analyze a hydrogen compatibility material evaluation method discussed in GTR and present a direction for the development of Korean-type hydrogen compatibility material evaluation methods.

• Journal of Radiation Protection and Research
• /
• 제46권1호
• /
• pp.14-23
• /
• 2021

Background: For radiological protection and control, the International Commission on Radiological Protection (ICRP) provides the nominal risk coefficients related to radiation exposure, which can be extrapolated using the excess relative risk and excess absolute risk obtained from the Life Span Study of atomic bomb survivors in Hiroshima and Nagasaki with the dose and dose-rate effectiveness factor (DDREF). Materials and Methods: Since it is impossible to directly estimate the radiation risk at doses less than approximately 100 mSv only from epidemiological knowledge and data, support from radiation biology is absolutely imperative, and thus, several national and international bodies have advocated the importance of bridging knowledge between biology and epidemiology. Because of the accident at the Tokyo Electric Power Company (TEPCO)'s Fukushima Daiichi Nuclear Power Station in 2011, the exposure of the public to radiation has become a major concern and it was considered that the estimation of radiation risk should be more realistic to cope with the prevailing radiation exposure situation. Results and Discussion: To discuss the issues from wide aspects related to radiological protection, and to realize bridging knowledge between biology and epidemiology, we have established a research group to develop low-dose and low-dose-rate radiation risk estimation methodology, with the permission of the Japan Health Physics Society. Conclusion: The aim of the research group was to clarify the current situation and issues related to the risk estimation of low-dose and low-dose-rate radiation exposure from the viewpoints of different research fields, such as epidemiology, biology, modeling, and dosimetry, to identify a future strategy and roadmap to elucidate a more realistic estimation of risk against low-dose and low-dose-rate radiation exposure.

• 방사성폐기물학회지
• /
• 제17권4호
• /
• pp.437-445
• /
• 2019

고리1호기의 영구정지 이후 해체공정에 대해 관심이 집중되고 있다. 방사선관리구역 내부 방사화구조물의 해체는 2026년 이후 본격적으로 진행될 예정이다. 원자로와 내부구조물은 원자력발전소의 구조물 중 가장 높은 수준의 방사능을 갖고 있으며 1차측의 대표적인 중량물로, 절단해체 과정에서 방사선학적 측면과 산업안전 측면에서 주의가 요구된다. 효율적인 해체 폐기물 관리를 달성하기 위해 원자로와 내부구조물의 절단해체공정에 대한 연구가 수행되었다. 방사화 평가결과 내부구조물의 노심 측면부와 상/하부의 일부는 중준위 폐기물로 평가되었고 이외의 구성품은 저준위로 평가되었다. 상대적으로 방사화가 많이 되고 복잡한 형상을 갖는 내부구조물의 경우 작업자의 피폭을 저감하기 위해 수중에서 다양한 절단방법을 통해 원격절단하는 방안이 제안되었고, 절단물은 약 19개의 극저준위/저준위 포장용기와 9개의 중준위 포장용기에 적재될 것으로 예상되었다. 방사화 평가결과 원자로의 노심 측면부는 저준위 폐기물로 평가되었고 이외의 부분은 극저준위 또는 자체처분수준의 폐기물로 확인되었다. 상대적으로 방사화가 적게 된 원자로의 경우 열적절단 방법을 사용해 현재위치에서 인양하며 공기중에서 원격절단하는 방안이 제안되었고, 절단물은 약 42개의 극저준위/저준위 포장용기에 적재될 것으로 예상되었다.

• 대한방사선기술학회지:방사선기술과학
• /
• 제38권2호
• /
• pp.163-170
• /
• 2015

후쿠시마 원전 사고 이후 수질 내 방사성 오염에 대한 국민들의 관심이 크게 높아졌다. 이에 따라 해외에서는 인체에 영향을 줄 수 있는 먹는 물 속 방사성물질 분석과 관리에 관한 연구가 활발히 진행되었다. 그리고 국내에서도 환경부령 제553호로 "먹는 물 수질기준 및 검사 등에 관한 규칙" 제 2조 수질기준을 규정하여 먹는 물 속 방사성농도의 감시를 하고 있으며 최근에는 염지하수 뿐 아니라 공공수역까지 범위를 확대하여 효율적인 관리를 하고 있다. 본 연구에서는 현재 국내에서 시행되고 있는 먹는 물 관리 시스템이 좀 더 나은 관리 및 운영이 될 수 있도록 미국 EPA(환경보호청) 사례를 분석해 보고자 하였다. 그 결과 미국 EPA(환경보호청)에서는 조사핵종을 선정할 시에 자국의 지질화학적인 조사와 원자력 발전소 보유현황 그리고 인공방사성 핵종의 사용유무 등을 조사하고 추가적으로 인간이 연간 먹는 물로 인하여 피폭 받을 수 있는 최대오염농도(0.1 mSv/y)를 고려함으로써 ${\alpha}$ 방출체, ${\beta}/{\gamma}$ 방출체, 라돈 및 우라늄으로 구분지어 핵종을 선정한 후 관리하고 있다. 조사주기 면에서는 미국 EPA(환경보호청)의 MCL(Maximum Contaminant Level - 최대오염농도)과 RDL(Required Detection Level - 검출하한치) 이라는 개념을 정립함으로써 그 이상의 농도가 검출되지 않도록 유지 및 관리를 하고 있다. 여기서 최대오염농도는 권고된 수치 이상의 농도가 측정 될 시에 특별한 관리조치와 해결방안이 제시되어야 하는 반면 검출하한치는 이 수치 이하로 측정된 방사성 농도는 인체에 영향이 없거나 거의 미미하므로 검출되었다 할지라도 특별한 조치가 필요 없다는 것이다. 예를 들어 최대오염농도 이상의 농도가 검출 될 시에는 기존에 조사해오던 주기보다 더 자주 측정하고 검출하한치 이하의 농도로 측정될 시에는 전에 해오던 주기대로 측정 및 관리를 하는 것이다. 이러한 각 핵종에 대하여 각각의 기준치를 정하고 미국 EPA(환경보호청)에서는 각 주(state)에 권한을 일임하여 자국의 주요 하천을 나누어 로드맵을 만들어 관리를 하고 있다. 그리고 그렇게 분류된 지역은 인력 및 예산에 맞게 HPGe, 형광검출기(NaI) 및 TLD 등의 검출기 등을 사용하여 효율적으로 측정값을 얻어 관리하고 있다.