• Nuclear Engineering and Technology
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• 제52권1호
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• pp.185-191
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• 2020

Plant-specific analyses of an advanced reactor have been performed to assure the structural integrity of the reactor pressure vessel during transient conditions, which are expected to initiate pressurized thermal shock (PTS) events. The vessel failure probabilities from the probabilistic fracture mechanics analyses are combined with the transient frequencies to generate the through-wall cracking frequencies, which are compared to the acceptance criterion. Several sensitivity analyses are performed, focusing on the orientations and sizes of cracks, the copper content, and a flaw distribution model. The results show that the integrity of the reactor vessel is expected to be maintained for long-term operation beyond the design lifetime from the PTS perspective using the design data of the advanced reactor. Moreover, a fluence level exceeding 9×10¹⁹ n/㎠ is found to be acceptable, generating a sufficient margin beyond the design lifetime.

• 식품과학과 산업
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• 제51권1호
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• pp.26-36
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• 2018

Terahertz (THz) represents the portion of the electromagnetic radiation between the microwave and the infrared region and is within the frequency range of 0.1-10 THz. The ability of THz waves to pass through a wide variety of packaging materials, combined with their ability to characterize the molecular structure of many substances makes it an attractive tool for the application of food quality and safety management. This review provides current information on application of THz spectroscopy/imaging technology for food quality and safety management. The THz spectroscopy/imaging technology has been shown to be useful for detecting foreign bodies, vitamin/moisture, pesticides, antibiotics, melamine etc. However, major barriers to the adoption of THz spectroscopy/imaging for food quality and safety management include THz signal loss in heterogeneous food matrices, high costs of sources and detectors, and absence of a library for the wide group of food compounds. Further research is needed to overcome these barriers.

• 한국철도학회:학술대회논문집
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• 한국철도학회 2003년도 추계학술대회 논문집(II)
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• pp.229-234
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• 2003

In this paper, the elemental components and improving purpose in advanced safety management system are reviewed to cope with a railway fire accident. And a considering procedure(V-cycle) of long-term plan for railway fire safety improvement is proposed. For the purpose of preventing recurrence of accident, items which have to be considered in the course of accident investigation and cause analysis are presented according to the stage of investigation activity.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2003년도 춘계학술발표대회 요약집
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• pp.120-120
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• 2003

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 1995년도 추계학술발표회논문집(1)
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• pp.191-196
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• 1995

The intelligent human-machine interface (HMI) has been developed to enhance the safety and availability of a nuclear power plant by improving operational reliability The key elements of the HMI are the large display panels which present synopsis of the plant status and the compact, digital work stations for the primary operator control and monitoring functions. The work station consists of four consoles such as a dynamic alarm console (DAC), a system information console (SIC), a computerized operating-procedure console (COC), and a safety related information console (SRIC). The DAC provides clean alarm pictures, in which information overlapping is excluded and alarm impacts are discriminated, for quick situation awareness. The SIC covers a normal operation by offering all necessary plant information and control functions. In addition, it is closely linked with the DAC and the COC to automatically display related system information under the request of these consoles. The COC aids the operator with proper emergency operation guidelines so as to shutdown the plant safely, and it also reduces his physical/mental burden by automating the operating procedures. The SRIC continuously displays safety related information to allow the operator to assess the plant status focusing on plant safety. The proposed HMI has been validated and demonstrated with on-line data obtained from the full-scope simulator for Yonggwang Units 1,2.

• 한국안전학회지
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• 제19권4호
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• pp.129-134
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• 2004

Educational programs for promoting occupational safety and health have widely been established in advanced countries, such as United States and Germany, in the area of disaster prevention Focused attentions and investments for safety and health education have been placed especially for small and medium sized companies. Recently, information technologies have also been applied for the development and management of educational programs in those countries. It is also worth noting that a wide variety of incentive systems has been implemented for managers and workers to voluntarily Participate in safety and health education. Based on the brief survey on incentive systems in advanced countries, this study proposes two different incentive models, such as 'Supervision Exemption Model for Participants in Safety and Health Education' and 'Compensation Program fur Educational Expenses and Losses', which may efficiently be employed in Korea. These incentive models may contribute to revitalizing the occupational safety and health education which has recently been dwindled due to the changes in governmental regulations.

• 한국안전학회지
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• 제28권3호
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• pp.123-128
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• 2013

The Advanced Power Reactor Plus(APR+), which is a GEN III+ reactor based on the APR1400, is being developed in Korea. In order to enhance the safety of the APR+, a passive auxiliary feedwater system(PAFS) has been adopted in the APR+. The PAFS replaces the conventional active auxiliary feedwater system(AFWS) by introducing a natural driving force mechanism while maintaining the system function of cooling the primary side and removing the decay heat. As the PAFS completely replaces the conventional AFWS, it is required to verify the cooling capacity of PAFS for the core damage frequency(CDF) evaluation. For this reason, this paper discusses the cooling performance of the PAFS during transient accidents. The test case and scenarios were picked from the result of the sensitivity analysis in APR+ Probabilistic Safety Assessment(PSA). The analysis was performed by the best estimate thermal-hydraulic code, RELAP5/.MOD3.3. This study shows that the plant maintains the stable state without the core damages under the given test scenarios. The results of PSA considering this analysis' results shows that the CDF values are decreased. The analysis results can be used for more realistic and accurate performance of a PSA.

• 한국안전학회지
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• 제22권5호
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• pp.57-64
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• 2007

In the field of domestic construction demolition works, work process management system is left behind compared with that of several advanced countries such as US, Japan and UK. Especially, the problems regarding safety management are more serious in terms of the availability of safety manuals and law system. The analysis results fiom the questionnaire survey and interviews with demolition engineers indicated that current safety management practices in demolition works lack systematic approach and inappropriate in securing labors' safe working environment. In addition, field labors and managers strongly requested the improvement of safety educational system. Grounded upon the analyses results and investigations, suggestions were drawn for the establishment of advanced safety educational system.

• 한국항행학회논문지
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• 제19권2호
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• pp.91-97
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• 2015

이 논문은 항공 분야에서의 안전필수 소프트웨어를 평가하기 위한 고려사항을 기술한다. 항공 분야에서의 안전필수 소프트웨어의 평가를 수행하기 위해서는 해당 소프트웨어의 평가 수준에 대한 정보가 필요하다. 그 수준은 표준에 명시되어 있으나 소프트웨어 자체적으로 결정되는 요소가 아니며 시스템 안전 평가 결과 및 시스템 설계 결과에 의존적이다. 그러므로 소프트웨어 평가수준을 결정하기 위해 시스템 개발 및 시스템 안전 평가 표준에서 필요로 하는 정보에 대해 설명한다. 그리고 소프트웨어를 평가하기 위한 기존의 방법론들을 조사하고 항공기 지상 유도 및 통제 시스템 소프트웨어의 평가에 적용할 방법을 제시한다.

• Nuclear Engineering and Technology
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• 제42권1호
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• pp.37-46
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• 2010

The development of advanced nuclear fuel cycle(ANFC) technology is essential to meet the national mission for energy independence via a nuclear option in Korea. The action target is to develop environmentally friendly, cost-effective measures to reduce the burden of long term disposal. The proper scenarios regarding potential radionuclide release from a repository have been developed in this study based on the advanced korean Reference Disposal System(A-KRS). To predict safety for the various scenarios, a new assessment code based on the GoldSim software has also been developed. Deterministic analysis indicates an environmental benefit from the ANFC as long as the solid waster from the ANFC act as a proper barrier.