• Title/Summary/Keyword: Safety critical systems

Search Result 480, Processing Time 0.032 seconds

The Study on Risk and Redundancy Assessment Methodology of Ship Machinery System (선박의 의장시스템에 대한 안전성 및 Redundancy 평가 방법론 연구)

  • Moon, Kyung-Tae;Yang, Young-Soon;Youn, Yeo-Pyo;Ryu, Won-Sun
    • Journal of the Society of Naval Architects of Korea
    • /
    • v.47 no.1
    • /
    • pp.76-87
    • /
    • 2010
  • According to the new rules and regulations (New SOLAS), major safety critical systems are to be designed to be redundant, which is called 'Redundancy Design'. This paper was to quantitatively analyze the degree of influence of the redundancy design applied to major safety critical systems using IMO's FSA(formal Safety Assessment) method. For the purpose of this study, the diesel engine system, which is actually one of major safety critical systems, was dealt with FMEA, FTA and ETA technique. In addition, whether the redundancy was met or not was verified and the degree of safety, or redundancy, was represented in terms of reliability. In conclusion, the safety of propulsion systems is possibly assessed systematically by estimating the risk level in terms of frequency and fatality.

NuSEE: AN INTEGRATED ENVIRONMENT OF SOFTWARE SPECIFICATION AND V&V FOR PLC BASED SAFETYCRITICAL SYSTEMS

  • Koo, Seo-Ryong;Seong, Poong-Hyun;Yoo, Jun-Beom;Cha, Sung-Deok;Youn, Cheong;Han, Hyun-Chul
    • Nuclear Engineering and Technology
    • /
    • v.38 no.3
    • /
    • pp.259-276
    • /
    • 2006
  • As the use of digital systems becomes more prevalent, adequate techniques for software specification and analysis have become increasingly important in nuclear power plant (NPP) safety-critical systems. Additionally, the importance of software verification and validation (V&V) based on adequate specification has received greater emphasis in view of improving software quality. For thorough V&V of safety-critical systems, V&V should be performed throughout the software lifecycle. However, systematic V&V is difficult as it involves many manual-oriented tasks. Tool support is needed in order to more conveniently perform software V&V. In response, we developed four kinds of computer aided software engineering (CASE) tools to support system specification for a formal-based analysis according to the software lifecycle. In this work, we achieved optimized integration of each tool. The toolset, NuSEE, is an integrated environment for software specification and V&V for PLC based safety-critical systems. In accordance with the software lifecycle, NuSEE consists of NuSISRT for the concept phase, NuSRS for the requirements phase, NuSDS for the design phase and NuSCM for configuration management. It is believed that after further development our integrated environment will be a unique and promising software specification and analysis toolset that will support the entire software lifecycle for the development of PLC based NPP safety-critical systems.

Multivariate analysis of critical parameters influencing the reliability of thermal-hydraulic passive safety system

  • Olatubosun, Samuel Abiodun;Zhang, Zhijian
    • Nuclear Engineering and Technology
    • /
    • v.51 no.1
    • /
    • pp.45-53
    • /
    • 2019
  • Thermal-hydraulic passive safety systems (PSSs) are incorporated into many advanced reactor designs on the bases of simplicity, economics and inherent safety nature. Several factors among which are the critical parameters (CPs) that influence failure and reliability of thermal-hydraulic (t-h) passive systems are now being explored. For simplicity, it is assumed in most reliability analyses that the CPs are independent whereas in practice this assumption is not always valid. There is need to critically examine the dependency influence of the CPs on reliability of the t-h passive systems at design stage and in operation to guarantee safety/better performance. In this paper, two multivariate analysis methods (covariance and conditional subjective probability density function) were presented and applied to a simple PSS. The methods followed a generalized procedure for evaluating t-h reliability based on dependency consideration. A passively water-cooled steam generator was used to demonstrate the dependency of the identified key CPs using the methods. The results obtained from the methods are in agreement and justified the need to consider the dependency of CPs in t-h reliability. For dependable t-h reliability, it is advisable to adopt all possible CPs and apply suitable multivariate method in dependency consideration of CPs among other factors.

Safety Critical I&C Component Inventory Management Method for Nuclear Power Plant using Linear Data Analysis Technic

  • Jung, Jae Cheon;Kim, Haek Yun
    • Journal of the Korean Society of Systems Engineering
    • /
    • v.16 no.1
    • /
    • pp.84-97
    • /
    • 2020
  • This paper aims to develop an optimized inventory management method for safety critical Instrument and Control (I&C) components. In this regard, the paper focuses on estimating the consumption rate of I&C components using demand forecasting methods. The target component for this paper is the Foxboro SPEC-200 controller. This component was chosen because it has highest consumption rate among the safety critical I&C components in Korean OPR-1000 NPPs. Three analytical methods were chosen in order to develop the demand forecasting methods; Poisson, Generalized Linear Model (GLM) and Bootstrapping. The results show that the GLM gives better accuracy than the other analytical methods. This is because the GLM considers the maintenance level of the component by discriminating between corrective and preventive.

Performance measurement of safety-critical systems based on ordinary differential equations and Petri nets: A case study of nuclear power plant

  • Nand Kumar Jyotish;Lalit Kumar Singh;Chiranjeev Kumar
    • Nuclear Engineering and Technology
    • /
    • v.55 no.3
    • /
    • pp.861-869
    • /
    • 2023
  • This article proposes a novel approach to measure the performance of Safety-Critical Systems (SCS). Such systems contain multiple processing nodes that communicate with each other is modeled by a Petri nets (PN). The paper uses the PN for the performance evaluation of SCS. A set of ordinary differential equations (ODEs) is derived from the Petri net model that represent the state of the system, and the solutions can be used to measure the system's performance. The proposed method can avoid the state space explosion problem and also introduces new metrics of performance, along with their measurement: deadlock, liveness, stability, boundedness, and steady state. The proposed technique is applied to Shutdown System (SDS) of Nuclear Power Plant (NPP). We obtained 99.887% accuracy of performance measurement, which proves the effectiveness of our approach.

The Software Verification and Validation Tasks for a Safety Critical System in Nuclear Power Plants

  • Cheon Se Woo;Cha Kyung Ho;Kwon Kee Choon
    • International Journal of Safety
    • /
    • v.3 no.1
    • /
    • pp.38-46
    • /
    • 2004
  • This paper introduces the software life-cycle V&V (verification and validation) tasks for the KNICS (Korea nuclear instrumentation and control system) project. The objectives of the V&V tasks are mainly to develop a programmable logic controller (PLC) for safety critical instrumentation and control (I&C) systems, and then to apply the PLC to developing the prototype of an engineered safety features-component control system (ESF-CCS) in nuclear power plants. As preparative works for the software V&V, various kinds of software plans and V&V task procedures have been developed according to the software life-cycle management. A number of software V&V tools have been adopted or developed to efficiently support the V&V tasks. The V&V techniques employed in this work include a checklist-based review and inspection, a requirement traceability analysis, formal verification, and life-cycle based software testing.

Safety Analysis and Design Model for a Complex System like ATM(Air Traffic Management) System (ATM(Air Traffic Management) 시스템과 같은 복잡 시스템의 안전 분석 및 설계 모델)

  • Park, Joong-Yong
    • Journal of the Korean Society of Systems Engineering
    • /
    • v.3 no.1
    • /
    • pp.27-31
    • /
    • 2007
  • A complex system like ATM(Air Traffic Management) has safety problem emerging from complex interactions between systems. In complex systems, malfunctions of components are not the only causes of critical accidents. To resolve this problem many researchers have proposed new safety analysis models for complex systems. This research is a way of improving safety analysis model focusing on systems engineering design model for ATM.

  • PDF

T&E Process for Safety-Critical CNS/ATM Systems (안전필수항행시스템의 시험평가 프로세스)

  • Kang, Ja-Young;Kim, Mu-Geun;Kim, Young-Hoon;Lim, In-Kyu
    • Journal of Advanced Navigation Technology
    • /
    • v.21 no.1
    • /
    • pp.50-57
    • /
    • 2017
  • Recently, safety-critical aviation system development programs promoted domestically have been terminated in the middle stage or they have not been put to practical use at the final stage. The program failure may be caused by various factors, but this study focused on imperfect test and evaluation(T&E) procedures. In general, T&E process of a safety-critical system must be distributed throughout the entire life-cycle of the system, have a continuity in phases, and can be implemented in a variety of ways depending on the maturity of the system development and acquisition strategy. This paper aims to present a new strategy by analyzing the domestic and overseas T&E processes to reduce the risk of domestic safety-critical CNS/ATM system development program and increase the success rate of program. First, we discuss the verification and validation techniques for safety-critical systems, analyze the T&E procedures of advanced institutes and the domestic situation, and then compare the domestic and overseas T&E processes to complement the imperfect testing procedure.

A study on the Correlation Hazard Analysis for Signaling System Safety (안전성 확보를 위한 위험원 분석 기법간 상관관계에 대한 연구)

  • Han, Chan-Hee;Lee, Young-Soo;Ahn, Jin;Jo, Woo-Sic
    • Proceedings of the KSR Conference
    • /
    • 2007.11a
    • /
    • pp.638-645
    • /
    • 2007
  • Computers are increasingly being introduced into safety and reliability critical systems. The safe and reliable operation of these systems cannot be taken for granted. Malfunctions of these systems can have potentially catastrophic consequences and they have already been involved in serious accidents. Software fault prevention, fault tolerance, fault removal and fault forecasting are the techniques to be used, implemented and verified for embedded software in critical systems as the contributors to safety and reliability of the software. To use them when developing a software product, a relationship must be established between them and the development processes, the methods and techniques to be used to develop software, as well as with the different product architectures. Railroad signaling system software is a safety-critical embedded software with realtime and high reliability requirements. The primary purpose of the safety management is to prevent the loss of lives or physical damages arising from potential hazards in the railroad signaling system. This study provides a systematic approach to analysis of potential hazards for their management during the system life cycle to assure the identification and definition of the most appropriate hazards.

  • PDF

Instrumentation and control systems design for nuclear power plant: An interview study with industry practitioners

  • Singh, Pooja;Singh, Lalit Kumar
    • Nuclear Engineering and Technology
    • /
    • v.53 no.11
    • /
    • pp.3694-3703
    • /
    • 2021
  • Instrumentation and Control systems (I&C) play a significant role in nuclear power plants (NPP) and other safety critical systems (SCS). We have conducted a rigorous study and discussions with experienced practitioners worldwide the strategy for the development of I&C systems to investigate the several aspects related to their dependability. We discussed with experienced practitioners that work on nuclear domain with the intention of knowing their approach, they use day-to-day for the development of such systems. The aim of this research is to obtain to provide guidance to those building I&C systems of NPP and have implications on state engineering licensure boards, in the determination of legal liability, and in risk assessment for policymakers, corporate governors, and insurance executives.