• Title/Summary/Keyword: Safety requirements

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Structural Design Requirements and Safety Evaluation Criteria of the Spent Nuclear Fuel Disposal Canister for Deep Geological Deposition (심지층 고준위폐기물 처분용기에 대한 설계요구조건 및 구조안전성 평가기준)

  • Kwon, Young-Joo;Choi, Jong-Won
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.5 no.3
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    • pp.229-238
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    • 2007
  • In this paper, structural design requirements and safety evaluation criteria of the spent nuclear fuel disposal canister are studied for deep geological deposition. Since the spent nuclear fuel disposal canister emits high temperature heats and much radiation, its careful treatment is required. For that, a long term(usually 10,000 years) safe repository for the spent nuclear fuel disposal canister should be secured. Usually this repository is expected to locate at a depth of 500m underground. The canister which is designed for the spent nuclear fuel disposal in a deep repository in the crystalline bedrock is a solid structure with cast iron insert, corrosion resistant overpack and lid and bottom, and entails an evenly distributed load of hydrostatic pressure from underground water and high pressure from swelling of bentonite buffer. Hence, the canister must be designed to withstand these high pressure loads. If the canister is not designed for all possible external loads combinations, structural defects such as plastic deformations, cracks, and buckling etc. may occur in the canister during depositing it in the deep repository. Therefore, various structural analyses must be performed to predict these structural problems like plastic deformations, cracks, and buckling. Structural safety evaluation criteria of the canister are studied and defined for the validity of the canister design prior to the structural analysis of the canister. And structural design requirements(variables) which affect the structural safety evaluation criteria should be discussed and defined clearly. Hence this paper presents the structural design requirements(variables) and safety evaluation criteria of the spent nuclear fuel disposal canister.

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AN ANALYSIS OF TECHNICAL SECURITY CONTROL REQUIREMENTS FOR DIGITAL I&C SYSTEMS IN NUCLEAR POWER PLANTS

  • Song, Jae-Gu;Lee, Jung-Woon;Park, Gee-Yong;Kwon, Kee-Choon;Lee, Dong-Young;Lee, Cheol-Kwon
    • Nuclear Engineering and Technology
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    • v.45 no.5
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    • pp.637-652
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    • 2013
  • Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security.. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system.

Hazard Identification and Testcase Design Method based on Use Case and HAZOP (사용사례와 HAZOP 기반의 위험원 식별 및 테스트케이스 설계 방안)

  • Do, Sungryong;Han, Hyuksoo
    • Journal of KIISE
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    • v.43 no.6
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    • pp.662-667
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    • 2016
  • As electric and electronic control systems have sharply increased in vehicles, safety accident has emerged as an important issue. Therefore, in order to ensure safety of the vehicle, engineers are required to identify the hazards utilizing PHA and HAZOP, etc. in the early phase of development and implement safety mechanisms to prevent them. HAZOP has been widely used in a systematic manner based on guidewords. However, HAZOP identifies malfunctions from the top-level functionality provided by the system, so it cannot sufficiently identify hazards during the system operation. This leads to restrictions in designing testcases, because the safety requirements are derived from only some of the hazards. This research aimed to provide a hazard identification method utilizing Use case description, which defines operation procedure of the system and HAZOP and a testcase design method based on safety requirements. We introduced a case study on Smart Key Control System in vehicles and compared with hazards identification results based on HAZOP, to demonstrate the effectiveness of this study. The result of this study could potentially reduce development cost and increase system quality by adequately identifying hazards and safety requirements and designing the related testcase.

Determination of Product and Certification Specification (제품 및 인증규격의 결정방법)

  • Choi, Sung-Woon
    • Proceedings of the Safety Management and Science Conference
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    • 2007.04a
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    • pp.457-465
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    • 2007
  • This paper introduces determination rules for specifications of quality characteristics and dependability requirements. This study also presents guidelines for various inclusions in standards such as environmental aspects, safety aspects, third-party certification systems, medical devices, and the needs of older persons and persons with disabilities.

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Electrical Characteristics of Catenary (Catenary 전기적 특성)

  • Gopal, Devarajan;Lho, Young-Hwan;Kim, Yoon-Ho
    • Proceedings of the KSR Conference
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    • 2007.05a
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    • pp.242-248
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    • 2007
  • In this paper, the basic requirements of catenary in railroad traction is explained. Three different types of catenary suspension systems for different terrains, environments and high speed / low speed trains are presented. The essential requirements of catenary such as reliability, cost effectiveness, maintenance and ruggedness requirements are discussed. The catenary materials and safety problems associated in it are dealt.

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A Study on the Architectural Design Requirements of the Korean e-Navigation System (한국형 e-Navigation 시스템의 아키텍쳐 설계 요건에 관한 연구)

  • Park, Sang-Kook;Yoon, Dae-Gwun;Park, Jung-Dae
    • Proceedings of the Korean Institute of Navigation and Port Research Conference
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    • 2015.07a
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    • pp.111-112
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    • 2015
  • IMO established an e-Navigation Strategy Implementation Plan(SIP) in 2014 and they aim to enforce in 2019. Accordingly, korean government also prepared e-Navigation SIP as the Next Maritime Safety Comprehensive Management System in 2015. The main content is to promote R&D by putting 131 billion won over the next five years from 2016 to 2020. On the other hand still in a situation that staying at the conception level of Korean e-Navigation System, by study the architectural design requirements of the Korean e-Navigation system, so we will be able to establish future research directions.

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A numerical and experimental approach for optimal structural section design of offshore aluminium helidecks

  • Seo, Jung Kwan;Park, Dae Kyeom;Jo, Sung Woo;Park, Joo Shin;Koo, Jeong Bon;Ha, Yeong Su;Jang, Ki Bok
    • Structural Engineering and Mechanics
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    • v.59 no.6
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    • pp.993-1017
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    • 2016
  • Helicopters are essential for supporting offshore oil and gas activities around the world. To ensure accessibility for helicopters, helideck structures must satisfy the safety requirements associated with various environmental and accidental loads. Recently, offshore helideck structures have used aluminium because of its light weight, low maintenance requirements, cost effectiveness and easy installation. However, section designs of aluminum pancakes tend to modify and/or change from the steel pancakes. Therefore, it is necessary to optimize section design and evaluate the safety requirements for aluminium helideck. In this study, a design procedure was developed based on section optimization techniques with experimental studies, industrial regulations and nonlinear finite element analyses. To validate and verify the procedure, a new aluminium section was developed and compared strength capacity with the existing helideck section profiles.

Thermal Evaluation of the KN-12 Transport Cask

  • Chung, Sung-Hwan;Chae, Kyoung-Myoung;Choi, Byung-Il;Lee, Heung-Young;Song, Myung-Jae
    • Journal of Radiation Protection and Research
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    • v.28 no.4
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    • pp.281-290
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    • 2003
  • The KN-12 spent nuclear fuel transport cask, which is a Type B(U) package designed to comply with the requirements of Korea Atomic Energy Act[1], IAEA Safety Standards Series No.TS-R-1[2] and US 10 CFR Part 71[3], is designed for carrying up to 12 PWR spent fuel assemblies in a basket structure. The cask has been licensed in accordance with Korea Atomic Energy Act and was fabricated in Korea in accordance with the requirements of ASME B&PV Sec.III, Div.3[4]. The cask must maintain thermal integrity in accordance with the related regulations and be evaluated to verify that the thermal performance of the cask complies with the regulatory requirements. The temperatures of the cask and components were determined by using finite elements methods with a numerical tool, safety tests using an 1/8 height slice model of the real cask were conducted to demonstrate verification of the numerical tool and methods, and heat transfer tests for normal transport conditions were performed as a fabrication acceptance test to demonstrate the heat transfer capability of the cask.

Comparative Analysis of Requirements for Information Presentation on In-vehicle Display Systems by Driving Career (운전 경력에 따른 차량 내 디스플레이 정보표시 요구사항 비교)

  • Gu, Bo Ram;Ju, Da Young
    • Transactions of the Korean Society of Automotive Engineers
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    • v.24 no.6
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    • pp.668-676
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    • 2016
  • The accelerated convergence of automobiles and ICT has led to an increase in in-vehicle electronic devices designed to enhance the safety and convenience of drivers. Consequently, the information presentation on in-vehicle display systems for drivers and passengers need to be taken into account in order to guarantee driving stability while satisfying the needs of UX-based design users. This study compared and evaluated requirements for information items shown on in-vehicle displays regarding driving safety and convenience by groups according to driving career. A total of 38 information items related to safety and convenience that can be displayed while driving and pulling over were collected. Their level of necessity was tested and evaluated by 234 drivers. Using the results, we conducted a comparative analysis on the requirements for information presentation on in-vehicle display systems by groups according to driving career.

Study on Development of Inter-acceptability Requirements of System Safety (시스템안전의 상호수용에 대한 요구사항 도출 연구)

  • Shin, Duc-Ko;Kim, Gon-Yop;Oh, Seh-Chan;Yoon, Yong-Ki
    • Proceedings of the KSR Conference
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    • 2011.10a
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    • pp.707-710
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    • 2011
  • System safety is defined as the state where the hazard risks due to internal system, interface, operation and maintenance are controlled as acceptable levels. It is represented and evaluated either with the risk level of each risk factor with the consideration of operation environments or with Safety Integrity Level (SIL) which is the system functional safety without considering application environments. The assessment results are issued in forms of certificates and they are reused in many cases. However, the conditions and restrictions for different application environments vary in each case, therefore, additional evaluation on the preconditions of assessment in comparison with the actual application environment must be carried out. For the area of train control, TR 50506-1 has been established based on the IEC 62425 (international standard for safety of train control system by RSSB) and EN 50129 (Europe standard) for the further assessment. In this paper, the analysis on TR 5056-1 has been conducted in depth. The purpose of the study is to determine the requirements for inter-acceptability including scope, procedures, principles, examination and suitability. The results can be utilized for the system safety maintenance when new devices or components are introduced in conventional systems.

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