• Journal of Radiation Protection and Research
• /
• 제35권1호
• /
• pp.6-11
• /
• 2010

Embodying the safety of radioactive waste disposal requires the relevant safety criteria and the corresponding stylized methods to demonstrate its compliance with the criteria. This paper proposes a conceptual model of risk-based safety evaluation for integrating complex potential radiation exposure situations in radioactive waste disposal. For demonstrating compliance with a risk constraint, the approach deals with important exposure scenarios from the viewpoint of the receptor to estimate the resulting risk. For respective exposure situations, it considers the occurrence probabilities of the relevant exposure scenarios as their probability of giving rise to doses to estimate the total risk to a representative person by aggregating the respective risks. In this model, an exposure scenario is simply constructed with three components:radionuclide release, radionuclide migration and environment contamination, and interaction between the contaminated media and the receptor. A set of exposure scenarios and the representative person are established from reasonable combinations of the components, based on a balance of their occurrence probabilities and the consequences. In addition, the probability of an exposure scenario is estimated on the assumption that the initiating external factors influence release mechanisms and transport pathways, and its effect on the interaction between the environment and the receptor may be covered in terms of the representative person. This integrated approach enables a systematic risk assessment for complex exposure situations of radioactive waste disposal and facilitates the evaluation of compliance with risk constraints.

• 대한안전경영과학회지
• /
• 제6권1호
• /
• pp.37-47
• /
• 2004

The processes of manufacturing FRP sewage disposal tanks are very dangerous and hazardous jobs for workers because of large size and heavy weight of the tank, toxic fiberglass dust, nasty smell, and dangerous tools such as hand-grinders. This paper introduces an automatic manufacturing system of the FRP sewage disposal tank to enhance the safety of workers. The system consists of 3 components: the FRP body rotation jig, the automatic manhole cutting machine, the automatic sanding processing machine. The safety of workers and working environment are greatly improved, because the dangerous jobs are automatized and the toxic fiberglass dust is automatically collected. Also, the productivity is greatly improved and the cost is reduced.

• 방사성폐기물학회지
• /
• 제12권4호
• /
• pp.335-344
• /
• 2014

우리나라 중 저준위 방사성폐기물의 처분시설개발을 위해 Safety Case 종합프로그램을 구축하였다. Safety Case 종합프로그램은 단계별 처분시설 종합개발을 위한 안전성판단과 계획수립을 목적으로 IAEA 등 국제기준을 참고하여 국내 환경에 적합하도록 구축하였다. 처분시설 종합안전성 확보체계는 최적화전략, 강건성전략, 논증가능성전략 및 심층방어전략에 따라 안전목표와 안전원칙을 만족하도록 구성하였다. 처분시설의 안전성은 평가기반의 품질에 따라 불확실성 저감을 위한 단계별 안전성평가와 안전성 수준의 확인 및 의사결정판단을 위한 다양한 신뢰성증진을 통해서 확보하도록 하였다.

• Journal of Radiation Protection and Research
• /
• 제35권4호
• /
• pp.142-150
• /
• 2010

중수로 사용후핵연료의 처분 효율을 높이기 위하여 새롭게 제안된 처분 시스템에 대한 방사선량을 MCNPX를 사용하여 계산함으로써 이 시스템의 방사선 안전성을 예비적으로 평가하고자 하였다. 이를 위해서 처분시스템의 각 요소에 대한 구성, 제원, 재질 등을 분석하였으며, 그에 상응하는 모델링을 수행하였다. 선량평가는 주요 구성요소에 대하여 수행하였으며, 평가결과 내부 구성요소에 대해서는 방사선량이 높은 편이었으나, 최종적인 처분시스템은 방사선에 대한 안전성이 높은 것으로 나타났다.

• 방사성폐기물학회지
• /
• 제14권4호
• /
• pp.385-410
• /
• 2016

경주 방사성폐기물 처분시설은 향후 80만 포장물을 처분할 계획이며 다양한 처분방식 및 관리형태를 가진 복합계가 될 것이다. 본 논문에서는 전체부지 처분용량(80만 포장물) 처분시설의 단계별 개발에 따른 영향을 평가하기 위하여 처분시설 종합개발계획(안)에 따른 예비안전성평가를 수행하였다. 각 시나리오에 대한 안전성평가결과 처분시설의 성능목표치를 만족하였다. 다만, 전체처분시설의 안전성 평가결과에 중준위 방사성폐기물로 인하여 1단계 동굴 처분시설이 가장 크게 영향을 미치므로 처분시설의 안전성 향상을 위하여 처분방사능량제한 설정 등 관리방안이 필요하다. Safety Case 단계별 구축을 통하여 중 저준위 방사성폐기물 처분시설 종합개발 과정에서 인지된 불확실성을 저감하여 안전성을 증진 시킬 수 있을 것으로 판단된다.

• 방사성폐기물학회지
• /
• 제20권4호
• /
• pp.511-521
• /
• 2022

Decommissioning of nuclear power plants generates a large amount of radioactive waste in a short period. Moreover, Radioactive waste has various forms including a large volumes of metal, concrete, and solid waste. The disposal of decommissioning waste using 200 L drums is inefficient in terms of economics, work efficiency, and radiation safety. Therefore, The Korea Radioactive Waste Agency is developing large containers for the packaging, transportation, and disposal of decommissioning waste. Assessing disposability considering the characteristics of the radioactive waste and facility, convenience of operation, and safety of workers is necessary. In this study, the exposure dose rate of workers during the disposal of new containers was evaluated using Monte Carlo N-Particle Transport code. Six normal and four abnormal scenarios were derived for the assessment of the dose rate in a near surface disposal facility operation. The results showed that the calculated dose rates in all normal scenarios were lower than the direct exposure dose limitation of workers in the safety analysis report. In abnormal scenarios, the work hours with dose rates below 20 mSv·y^-1 were calculated. The results of this study will be useful in establishing the optimal radiation work conditions.

• Nuclear Engineering and Technology
• /
• 제35권6호
• /
• pp.556-565
• /
• 2003

A quality assurance safety assessment database, called QUARK (QUality Assurance Program for Radioactive Waste Management in Korea), has been developed to manage both analysis information and parameter database for safety assessment of low- and intermediate-level radioactive waste (LILW) disposal facility in Korea. QUARK is such a tool that serves QA purposes for managing safety assessment information properly and securely. In QUARK, the information is organized and linked to maximize the integrity of information and traceability. QUARK provides guidance to conduct safety assessment analysis, from scenario generation to result analysis, and provides a window to inspect and trace previous safety assessment analysis and parameter values. QUARK also provides default database for safety assessment staff who construct input data files using SAGE(Safety Assessment Groundwater Evaluation), a safety assessment computer code.

• 방사성폐기물학회지
• /
• 제18권spc호
• /
• pp.21-36
• /
• 2020

With respect to spent nuclear fuels, disposal containers and bentonite buffer blocks in deep geological disposal systems are the primary engineered barrier elements that are required to isolate radioactive toxicity for a long period of time and delay the leakage of radio nuclides such that they do not affect human and natural environments. Therefore, the thermal stability of the bentonite buffer and structural integrity of the disposal container are essential factors for maintaining the safety of a deep geological disposal system. The most important requirement in the design of such a system involves ensuring that the temperature of the buffer does not exceed 100℃ because of the decay heat emitted from high-level wastes loaded in the disposal container. In addition, the disposal containers should maintain structural integrity under loads, such as hydraulic pressure, at an underground depth of 500 m and swelling pressure of the bentonite buffer. In this study, we analyzed the thermal stability and structural integrity in a deep geological disposal environment of the improved deep geological disposal systems for domestic light-water and heavy-water reactor types of spent nuclear fuels, which were considered to be subject to direct disposal. The results of the thermal stability and structural integrity assessments indicated that the improved disposal systems for each type of spent nuclear fuel satisfied the temperature limit requirement (< 100℃) of the disposal system, and the disposal containers were observed to maintain their integrity with a safety ratio of 2.0 or higher in the environment of deep disposal.

• 핵의학기술
• /
• 제21권2호
• /
• pp.13-27
• /
• 2017

국내 의료용 방사성폐기물 자체처분과 관련하여 심사과정에서 많은 보완을 거치게 되고, 이 과정을 통과함에 많은 어려움을 겪고 있다. 이에 따라 의료용 방사성폐기물의 자체처분시 기본적인 가이드라인을 제시함으로써 의료기관의 방사성 폐기물 처리효율을 높이고자 한다. 2015년부터 2016년까지 국내 15개 의료기관의 의료용 방사성폐기물 자체처분 절차서 및 계획서 작성 시 보완 요청된 사항들을 비교 검토하였으며, 이와 관련하여 원자력 안전법 관련 규정을 기준으로 방사성폐기물 자체처분 시 서류작성에 필요한 세부 작성안 들을 도출하였다. 한국원자력안전기술원의 대표적인 보완요청사항들로는 비가연성 폐기물의 처분방법, 자체처분 예정 폐기물의 저장방법, 폐기물 자체처분의 정당성 및 자체처분 전 조치사항, 배기필터의 기준방사능 및 보관기간 산출, 폐기물 수량 측정 용기 보유 여부 및 증빙자료, 감마카운터 사용 시 측정효율 증명자료 첨부임을 확인할 수 있었다. 또한 의료 방사성 폐기물 자체처분 가이드라인 구축을 통해 방사성동위원소 핵종 및 발생유형별 분류기준 등을 명확히 제시하였다. 이를 통해, 자체처분 서류 작성에 따른 시간의 단축과 업무대행 지출비용이 발생되지 않음을 확인할 수 있었고 방사성 폐기물의 장기간 보관에 따른 보관시설의 저장효율이 좋아지고 경제적 비용도 절감됨을 알 수 있었다. 본 가이드라인을 바탕으로 방사성폐기물 자체처분의 실무적인 어려움을 겪고 있는 관계자들의 업무효율 향상에 기여할 것으로 사료된다.

• 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.