• 제목/요약/키워드: Nuclear safety regulation

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원전설비 등급분류 방법론 분석 (Analysis of classification standards of nuclear facilities)

  • 제상윤;장윤석;오창식;최영환
    • 한국압력기기공학회 논문집
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    • 제14권1호
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    • pp.48-57
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    • 2018
  • Configuration management (CM) is the process of identifying and documenting characteristics of plant structures, systems and components (SSCs), and of ensuring that changes to these characteristics are properly assessed, approved, implemented, verified and recorded. The purpose of this study is to examine regulation and technical standards developed under different concepts and level of depth for classification of nuclear SSCs as an essential prerequisite of the CM. In this context, main contents of currently adopted NSSC Notice 2016-10 are reviewed and compared with those in recently published ANSI/ANS 58.14 and IAEA SSG-30. The technical standards were prototypically used for classification of O-rings in two nuclear systems. It is found that ANSI/ANS 58.14 results in different categories taking into account specific features while IAEA SSG-30 leads to same categorization of the O-rings. Key findings will be summarized for Korean regulatory amendment in the future.

How should the regulatory defaults be set?

  • Jang, Seung-Cheol
    • Nuclear Engineering and Technology
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    • 제50권7호
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    • pp.1099-1105
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    • 2018
  • How to choose defaults in risk-informed regulations depends on the conservatism implicated in regulatory defaults. Without a universal agreement on the approaches dealing with the conservatism of defaults, however, the desirability of conservatism in regulatory risk analyses has long been controversial. The opponent views it as needlessly costly and irrational, and the proponent as a form of protection against possible omissions or underestimation of risks. Moreover, the inherent ambiguity of risk makes it difficult to set suitable defaults in terms of risk. This paper, the extension of the previous work [1], focuses on the effects of different levels of conservatism implicated in regulatory defaults on the estimates of risk. According to the postulated behaviors of regulated parties and the diversity of interests of regulators, in particular, various measures for evaluating the effect of conservatism in defaults are developed and their properties are explored. In addition, a simple decision model for setting regulatory defaults is formulated, based on the understanding of the effect of conservatism implicated in them. It can help decision makers evaluate the levels of safety likely to result from their regulatory policies.

해외원전 비계획적 방출 및 한국의 환경감시 현황 분석 (Review of Unplanned Release at Foreign Nuclear Power Plants and Radiological Monitoring at Korean Power Plants)

  • 박수찬;함박눈;권장순;조동건;정지혜;권만재
    • 한국지하수토양환경학회지:지하수토양환경
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    • 제23권4호
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    • pp.1-15
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    • 2018
  • Despite of safety issues related to radiological hazards, 31 countries around the world are operating more than 450 nuclear power plants (NPPs). To operate NPPs safely, safety regulations from radiation protection organizations were developed and adopted in many countries. However, many cases of radionuclide releases at foreign NPPs have been reported. Almost all commercial NPPs routinely release radioactive materials to the surrounding environments as liquid and gas phases under control. These releases are called 'planned releases' which are planned, regularly monitored, and well documented. Meanwhile, the releases focused in this review, called 'unplanned releases', are neither planned nor monitored by regulatory and/or protection organizations. NPPs are generally composed of various structures, systems and components (SSCs) for safety. Among them, the SSCs near reactors are closely related to safety of NPPs, and typically fabricated to comply with stringent requirements. However, some non-safety related SSCs such as underground pipes may be constructed only according to commercial standards, causing the leakage of radioactive fluids usually containing tritium ($^3H$). This paper discusses SSCs of NPPs and introduces several cases of unplanned releases at foreign NPPs. The current regulation on the environmental radiological surveillance and assessment around the NPPs in South Korea are also examined.

원자력안전법 수시출입자 안전관리체계 개편에 대한 방사선학과 재학생들의 융합적 인식 연구 (A Study on the Convergence Perception of Students in Radiology on the Reorganization of Safety Management System by person with frequent access of Nuclear Safety Act)

  • 이보우;김창규
    • 한국융합학회논문지
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    • 제10권6호
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    • pp.89-94
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    • 2019
  • 이 연구는 원자력안전법 개정에 따른 수시출입자 안전관리체계 개편이 적용된 방사선학과 재학생들의 인식도를 알아보고자 K 대학교 방사선학과 재학생 175명을 대상으로 설문조사를 실시하였다. 원자력안전법에 의해 수시출입자로 분류되어 관리를 받을 필요가 있다고 인식하는 재학생은 2학년 98.1%, 3학년 90.3%, 4학년 97.7%로 나타났으며, 수시출입자로 구분되어 촬영실습의 조작에 제한을 받는다는 재학생이 2학년 96.3%, 3학년 74.2%, 4학년 93.2%로 나타났다. 방사선촬영실습에서 방사선장비를 조작하는데 제한을 두는 것은 학생들의 학습권을 침해하는 규정으로 학습에 대한 예외규정을 제정하여 학습권이 침해받지 않도록 정책을 펼쳐나가야 할 것 이다.

Study of the used deuterium absorption material disposal

  • Kim, Dong-Gyung;Kim, Myung-Chul;Lee, Bum-Sig;Lee, Sang-Gu
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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    • pp.64-72
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    • 2004
  • The dryer (ten per unit) are operating to remove tritium in PHWR(Pressurized Heavy Water Reactor). There are coming out heavy water adsorbent from operating the dryer (95 drums for ten year per unit) The amount of radioactivity of heavy water adsorbent almost exceed ninety times more than disposal limit-in-itself showed by The Ministry of Science and Technology. It has to be disposed whole radioactive waste products, however there are problems of increase at the expense of their permanent disposal. In this research, We have studied how to remove kinds of nuclear materials and amount of tritium with in heavy water adsorbent. As the result we could develop disposal equipment and apply it. D20 adsorbent have to contain below Gamma nuclide O.3Bq/g and tritium 100Bq/g "The Regulation for disposal of the radioactivity wastes" showed by The Ministry of Science and Technology. There fore. So as to remove amount of tritium and kinds of nuclear materials (DTO) we needed a equipment. Also we have studied how to remove effectively radioactivity with in Adsorbent. As cleaning heavy water adsorbent and drying on each condition (temperature for drying and hours for cleaning). Because there is something to return heavy water adsorbent by removing impurities within adsorbent when it is dried o high temperature. After operating, we have been applying this research to the way to dispose heavy water adsorbent. Through this we could reduce solid waste products and the expense of permanent disposal of radioactive waste products and also we could contribute nuclear power plant run safely. According to the result we could keep the best condition of radiation safety super vision and we could help people believe in safety with Radioactivity wastes control for harmony with Environment.

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원전 안전등급 비상디젤발전기 속도제어시스템 성능개선 및 분석에 관한 연구 (Performance upgrade and analysis report for nuclear safety related emergency diesel generator speed control system)

  • 김윤식;전일영;이성근;김창국;안진우
    • 전력전자학회:학술대회논문집
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    • 전력전자학회 2005년도 전력전자학술대회 논문집
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    • pp.581-583
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    • 2005
  • The paper is final report for speed control upgrade and analysis report which recently performed on PWR NPP safety related EDG KHNP Ulchin NPP No.2 Unit. The upgraded system includes more beneficial function like as 'Slow start with starting ramp', 'Generator load sensing & control capability' and 'Emergency ramp during slow start'. This paper shows functional operation of slow start regime according to NRC regulatory guide which guide regulation to NPP safety related environment.

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의료기관의 방사선사 중 방사선 관계종사자와 방사선 작업종사자의 이원화 체계에 따른 인식도 조사 (A Survey on the Awareness of Radiation-related Workers and Radiation Workers in the Medical Institutions According to the Dual System)

  • 허미;안성민
    • 대한방사선기술학회지:방사선기술과학
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    • 제41권5호
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    • pp.479-485
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    • 2018
  • Radiologic technologists working at the second and third medical institutions are classified as radiation-related workers and radiation workers according to their working departments, and are subject to double regulation by the Ministry of Health and Welfare and the Nuclear Safety Commission. We will try to understand the system of dualization and to understand the investigation of recognition. The dualized system of radiation-related workers and radiation workers includes the difference in name and terminology, the effective dose limit, the maintenance education and training of radiologic technologists, the period of medical examination, the radiation zone, dose of the woman whose pregnancy is confirmed in radiologic technologists, the qualification criteria of the safety officer, and the period of the regular inspection of the radiological equipment. In the questionnaire survey on the dualization system, there were various items showing significant differences between the radiation-related workers and radiation workers Overall, the radiation workers were more aware of the radiation workers' education and related terms than the radiation-related workers.

방사성 요오드 치료 후, 퇴원 선량 측정에 있어 각국의 기준 및 권고 비교 (The Study on the Dilution Time of Radioactive Tracer in Estradiol Measurement)

  • 이승재;서수현;이성하;박용성;오기백;김재삼
    • 핵의학기술
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    • 제21권2호
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    • pp.49-54
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    • 2017
  • Purpose The high-dose administration of I-131 has been standing for the basic therapy method of thyroid cancer. In korea, it is not necessary for patients to be hospitalized if the administration dose are under 1.2 GBq. However, if the dose are over 1.2 GBq, the patients should be stay in special ward with radiation shield. In such cases, the radioactivity level upon release should be under a dose of $70{\mu}Sv/hr$ at a distance of approx. 1m. This regulation bring the patients to stay for about 2 to 3 days in ward before the release. Materials and Methods Using the inpatients' release data of severance hospital, an inpatient-days were retrospectively calculated and compared with practical data and estimate the inpatient-days with the conditions of korea ($70{\mu}Sv/hr$), Japan ($30{\mu}Sv/hr$), germany ($3.5{\mu}Sv/hr$ at a distance of approx. 2 m), and other european countries. Results When a effective half-life of 15.4 was used, the expected inpatient-days were calculated as 2.15 days in the condition of Japanese regulation and 1.37 days in the condition of korean regulation. The practical inpatient-days of patients in Severance hospital were 1.32 days. Conclusion As ICRP 94 has been mentioned that the release of patients administrated with I-131 for the therapy should be carefully considered because each patients has different thyroid uptake rate and their conditions with family members after the release from the ward. Nonetheless, efforts to bring more aquate data which is for getting closer to the practical data should be continuously studied.

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Voltage Sags Impact on CAR and SOR of HANARO

  • Kim, Hyung-Kyoo;Jung, Hoan-Sung;Wu, Jong-Sup
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 2004년도 추계학술발표회 발표논문집
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    • pp.657-658
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    • 2004
  • The reactor protection system (RPS) of HANARO is a safety class system. The reactor is tripped by dropping four shut off rods (SOR). The SOR system consists of a SOR, hydraulic pump, hydraulic cylinder, solenoid valves and a power supply unit which has the AC coil contactor as a switching component. The hydraulic pump lifts up the SOR. The SOR drops by loss of the hydraulic pressure in the hydraulic circuit at the occurrence of voltage sags or interruptions. From this experiment, we knew that the magnitude of the voltage sag which impacts on this system is 70V, 500msec. The reactor regulation system (RRS) of HANARO has four CARs which are connected to the driver through a magnetic clutch. The CAR drops by loss of electromagnetic force of the magnetic clutch when the deeper voltage sags to lower than 10V, 500msec.

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RADIOACTIVE SOURCE SECURITY: WHY DO WE NOT YET HAVE A GLOBAL PROTECTION SYSTEM?

  • Englefield, C.
    • Nuclear Engineering and Technology
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    • 제46권4호
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    • pp.461-466
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    • 2014
  • Security of radioactive sources has been an issue since the earliest days of safety regulation of such materials. Since the events of September 11 2001, some governments and regulatory bodies have been much more focussed on these issues and have introduced extensive and enhanced security arrangements. International organisations like the IAEA and WINS have worked hard to help States in this regard. However, only a minority of States have implemented statutory security systems for radioactive source security. Why have so many States still to take action? What can be done to encourage and support these changes? This paper will offer some possible explanations for the lack of action in so many States and some potential answers to these questions.