• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4367-4381
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• 2023

Nuclear power plants are increasingly being equipped with digital I&C systems. Although some probabilistic safety assessment (PSA) models for the digital I&C of nuclear power plants have been constructed, there is currently no specific internationally agreed guidance for their modeling. This paper presents an initiative by the OECD Nuclear Energy Agency called "Digital I&C PSA - Comparative application of DIGital I&C Modelling Approaches for PSA (DIGMAP)", which aimed to advance the field towards practical and defendable modeling principles. The task, carried out in 2017-2021, used a simplified description of a plant focusing on the digital I&C systems important to safety, for which the participating organizations independently developed their own PSA models. Through comparison of the PSA models, sensitivity analyses as well as observations throughout the whole activity, both qualitative and quantitative lessons were learned. These include insights on failure behavior of digital I&C systems, experience from models with different levels of abstraction, benefits from benchmarking as well as major contributors to the core damage frequency and those with minor effect. The study also highlighted the challenges with modeling of large common cause component groups and the difficulties associated with estimation of key software and common cause failure parameters.

• 한국방사선학회논문지
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• 제15권3호
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• pp.355-359
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• 2021

본 연구에서는 교내 실습 중 방사선(학)과 에 지정된 방사선작업종사자 및 수시출입자의 피폭 정도를 분석하여 방사선(학)과에 대한 원자력안전법의 방사선 방호에 대한 타당성과 최적화에 대한 기초 연구에 목적을 두었다. 연도별 작업종사자의 평균 피폭선량 2014년과 2016년에 0.01 mSv로 가장 낮은 수치가 나타났으며. 가장 높은 수치는 2018년도로 0.12 mSv이다. 연도별 수시출입자의 평균 피폭선량은 2018년 0.013 mSv로 가장 낮은 수치를 보였으며, 2016년 0.022 mSv로 가장 높은 수치가 나타났다. 본 연구를 통하여 방사선 발생장치만을 사용하는 대학의 담당교수, 실습 조교 및 방사선(학)과의 학생들은 교내실습 과정에서 받는 연간 피폭선량은 일반인의 선량한도인 1mSv에도 미치지 못하는 수준이다. 그러므로 방사선(학)과 학생들의 피폭선량이 일반인의 선량한도 보다 낮게 나오는 시점에서 현재 원자력안전법의 안전규제는 과도한 규제라고 판단된다. 따라서 현재의 원자력안전법에서 방사선 발생장치의 규정을 개정하거나 대학의 재학생에 대한 방사선안전관리 체계를 수정하는 것은 필요하다고 사료된다.

• 핵의학기술
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• 제17권1호
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• pp.3-6
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• 2013

Purpose: The treatment of thyroid cancer patients was continuously increased. According to the increment of thyroid cancer patients, the establishment of iodine therapy site was also increased in each hospital. This treatment involves the administration of radioactive iodine, which will be given in the form of a capsule. Therefore, protections and managements for radioactive source pollution and radiation exposure should be necessary for radiation safety. Among the many problems, the problem of disposing the radioactive wastes was occurred. In this study, The date for self-disposal for radioactive wastes, which were contaminated in clothes, bedclothes and trash, were calculated. Materials and Methods: The number of iodine therapy ward was 15 in Korea Institute of Radiological Medical and Sciences. Recently, 8 therapy wards were operated for iodine therapy patients and others were on standby for emergency treatment ward of any radiation accidents. Radioactive wastes, which were occurred in therapy ward, were clothes, bedclothes, bath cover for patients washing water and food and drink which was leftover by patients. Each sample was hold into the marinelli beaker (clothes, bedclothes, bath covers) and 90 ml beaker (food, drink, and washing water). The activities of collected samples were measured by HpGe MCA device (Multi Channel Analysis, CANBERRA, USA) Results: The storage period for the each kind of radioactive wastes was calculated by equation of storage periods based on the measurement outcomes. The average storage period was 60 days for the case of clothes, and the maximum storage period was 93 days for patient bottoms. The average storage period and the maximum storage period for the trash were 69 days and 97 days, respectively. The leftover foods and drinks had short storage period (the average storage period was 25 days and maximum storage period was 39 days), compared with other wastes. Conclusion: The proper storage period for disposing the radioactive waste (clothes, bedclothes and bath cover) was 100 days by the regulation on self-disposal of radioactive waste. In addition, the storage period for disposing the liquid radioactive waste was 120 days. The current regulation for radioactive waste self-disposing was not suitable for the circumstances of each radioactive therapy facility. Therefore, it was necessary to reduce the leftover food and drinks by adequate table setting for patients, and improve the process and regulation for disposing the short-half life radioactive wastes.

• 핵의학기술
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• 제15권2호
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• pp.104-110
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• 2011

Purpose: 최근 의료기관에 대한 객관적인 평가방법은 의료기관 인증제도를 시행하여 의료서비스에 대한 수요자의 신뢰성을 높이고 있다. 또한 핵의학 검사실과 진단검사의학 검사실도 국제적인 여러 종류의 인증제도를 채택하면서 검사실내의 안전관리에 관한 사항이 중요시 되고 있다. 핵의학과 혈액검사실에서도 검체에 의한 감염 및 방사성 동위원소시약을 비롯한 여러 유해환경에 노출되어 있으므로 직원 및 환자의 안전관리 영역에 많은 관심이 요구된다. 이에 본원 핵의학과 혈액검사실에서 실시하고 있는 직원 및 환자의 안전관리 활동에 대해 논해 보고자 한다. Material & Method: 본원 핵의학과 혈액검사실에서는 안전관리 책임자에 의해 전반적인 안전관리 사항이 제시되고 검사실 모든 직원이 이를 업무에 적용하고 있다. 정해진 규정에 따라 안전관리 교육을 정기적으로 실시하고 있으며, 검사 업무 중에는 개인 보호구 착용 및 손 위생을 시행하여 감염을 예방하고 있다. 또한 기술적 안전지침과 정전으로 발생되는 사고지침을 통해 유사시에 대비하고 있다. 감염관리 지침을 통해 감염 예방 및 감염 시 대비 요령을 숙지하고 방사성 동위원소 관리, 시약 사용에 대한 안전관리 및 유해화학 물질에 대한 안전 지침을 업무에 적용하고 있다. Result: 핵의학과 혈액검사실에서는 안전관리 규정을 업무에 적용하고 있다. 손 위생을 실시해야 하는 상황에서 손 씻기를 시행하여 직원 및 환자 간 감염을 예방하고 있으며, 검체에 의한 감염을 예방하고자 개인 보호구 착용을 하고 있다. 혈액검사실 내에서 사용하고 있는 시약에서 유해물질로 분류된 시약은 쉽게 알아 볼 수 있도록 분리하여 보관하며 방사성 폐기물 및 일반 의료 폐기물도 효율적으로 안전한 관리를 하고 있다. 이와 같은 많은 안전관리 활동을 통해 직원들은 안전관리 의식이 향상 되었으며 환자들은 여러 위험으로부터 보호되고 있다. Conclusion: 핵의학과 혈액검사실 직원은 안전관리에 대한 규정을 충분히 숙지하고 업무에 적용해야 한다. 더 나은 안전관리에 대한 제안이 나오면 검토하여 적용하고 직원 및 환자의 안전관리에 대한 질적 향상을 높여야 할 것으로 사료된다.

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4499-4513
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• 2022

Spent fuel behavior of dry storage was simulated in a continuous state from steady-state operation by modifying FRAPCON-4.0 to incorporate spent fuel-specific fuel behavior models. Spent fuel behavior of a typical PWR was compared with that of NuScale Power Module (NPM^TM). Current PWR discharge burnup (60 MWd/kgU) gives a sufficient margin to the hoop stress limit of 90 MPa. Most hydrogen precipitation occurs in the first 50 years of dry storage, thereby no extra phenomenological safety factor is identified for extended dry storage up to 100 years. Regulation for spent fuel management can be significantly alleviated for LWR-based SMRs. Hydride embrittlement safety criterion is irrelevant to NuScale spent fuels; they have sufficiently lower plenum pressure and hydrogen contents compared to those of PWRs. Cladding creep out during dry storage reduces the subchannel area with burnup. The most deformed cladding outer diameter after 100 years of dry storage is found to be 9.64 mm for discharge burnup of 70 MWd/kgU. It may deteriorate heat transfer of dry storage by increasing flow resistance and decreasing the view factor of radiative heat transfer. Self-regulated by decreasing rod internal pressure with opening gap, cladding creep out closely reaches the saturated point after ~50 years of dry storage.

• Nuclear Engineering and Technology
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• 제49권8호
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• pp.1772-1777
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• 2017

Korean nuclear power plants (NPPs) periodically evaluate the radioactive gaseous and liquid effluents released from power reactors to protect the public from radiation exposure. This paper provides a comprehensive overview of the release of radioactive effluents from Korean NPPs and the effects on the annual radiation doses to the public. The amounts of radioactive effluents released to the environment and the resulting radiation doses to members of the public living around NPPs were analyzed for the years 2011-2015 using the Korea Hydro & Nuclear Power Co., Ltd's annual summary reports of the assessment of radiological impact on the environment. The results show that tritium was the primary contributor to the activity in both gaseous and liquid effluents. The averages of effective doses to the public were approximately on the order of $10^{-3}mSv$ or $10^{-2}mSv$. Therefore, even though Korean NPPs discharged some radioactive materials into the environment, all effluents were within the regulatory safety limits and the resulting doses were much less than the dose limits.

• Nuclear Engineering and Technology
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• 제19권4호
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• pp.266-278
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• 1987

이 논문은 원자력발전소의 안전성 규제를 위한 성능 기준을 설정하는데 야기되는 몇가지 문제점을 다룬다. 저층 성능 기준을 설정하는 것이 고충 성능 기준을 설정하는 것보다 훨씬 더 어려운 과제이기 때문에, 저층 성능 기준은 보다 쉽게 결정될 수 있는 고충 성능기준으로부터 그와 부합되게 유도되어야 한다. 본 논문은 또한, 평균치-평균치 mapping에 의거한 신뢰도 할당 방법론을 상태변수가 불확실한 stochastic 다목적 최적화 문제로 적용 확장함으로써 성능 기준의 불확실성을 규명하는 몇 가지 방법을 제안한다.

• 핵의학기술
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• 제21권2호
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• pp.13-27
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• 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.

• 대한방사선기술학회지:방사선기술과학
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• 제45권2호
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• pp.159-164
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• 2022

The study developed a radiation dose measurement program in the radiology laboratory to measure how much exposure the students are exposed to during the radiology class, to request for the improvement and the revision of the current Nuclear Safety Act. The experimental program is shown in the following figure, and experiments were conducted to determine the degree of radiation exposure in the control room with a lead gown at a distance of 1 m, 2 m, and 1 m, and in a control room with a radiographic lead glass wall. The duration of the experiment was 3 months from April to June, when radiation imaging practice classes were conducted, and 128 hours of imaging practice per month were conducted. In order to find out the dose of radiation dose during radiology imaging practice class, the experiment was carried out from April to June for 3 months, and according to the program, the results of exposure dose were 0.34 mSv at 1 m distance, 0.01 mSv at shielding of lead gown at 1 m distance, 0.16 mSv at 2 m distance, and 0.01 mSv at control room with radiation lead glass wall. The exposure dose from the test results was much below the annual general public limit dose of 1 mSv. The restriction on the operation of the radiation equipment in the practice of the students is a regulation that infringes the right of students to learn, and amendments or exemptions of Nuclear Safety Act should be enacted to ensure that it does not violate the fundamental right to learn for students in radiology.

• 제어로봇시스템학회논문지
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• 제19권4호
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• pp.328-333
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• 2013

Since a slight malfunction of control systems in a nuclear power plant may cause huge catastrophes, such control systems usually have multiple redundancy and reliable features, and their reliability and availability should be analyzed and verified thoroughly. This paper performed the reliability analysis of the SPLC (Safety Programmable Logic Controller) that is under developed as the control systems for the next generation nuclear power plant. One of the key features of SPLC is that it has multiple redundancy modes as faults happen, which means the reliability analysis for one fixed redundant model is not enough to analyze the reliability of SPLC. With considering this reconfigurable concept, FTA (Fault Tree Analysis) was used to capture fault-relationship among sub-modules. The analysis results show that MTTF (Mean Time to Fault) of SPLC is 45,080 hours, which is a about 4.5 times longer than the regulation, 10,000 hours.