• Title/Summary/Keyword: safety verification

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A Verification Method for the Integrated Model Combining SysML-Based System Failure Model and System Architecture (SysML 기반 시스템 고장 모델과 시스템 아키텍처의 통합 모델에 대한 검증 기법)

  • Jo, Jeong-Ho;Lee, Jae-Chon
    • Journal of the Korea Academia-Industrial cooperation Society
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    • v.17 no.8
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    • pp.77-83
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    • 2016
  • International standards for systems safety have been established in various areas of industry. Such standards recommend that safety design activities be carried out early on in the beginning of systems development. Hazard analysis should be done in close interaction with the conceptual design of the system. This paper focuses on how to verify whether the safety goals are met while considering system design issues. The architecture of the underlying system was first modeled using SysML, a systems modeling language, and then hazard analysis was performed based on architectural information to obtain a system failure model. Thereafter, an integrated model was developed by combining the SysML failure model and the architectural model, and then safety designs were added to prevent system failure. Finally, a simulation of the developed model was performed to see if a system functions even when some components are failing.

SIS Design for Fuel Gas Supply System of Dual Fuel Engine based on Safety Integrity Level(SIL) (이중연료엔진의 연료가스공급시스템에 대한 안전무결도 기반 안전계장시스템 설계)

  • Kang, Nak-Won;Park, Jae-Hong;Choung, Choung-Ho;Na, Seong
    • Journal of the Society of Naval Architects of Korea
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    • v.49 no.6
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    • pp.447-460
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    • 2012
  • In this study, the shutdown system of the fuel gas supply system is designed based on the Safety Integrity Level of IEC 61508 and IEC 61511. First of all, the individual risk($10^{-4}$/year) and the risk matrix which are the risk acceptance criteria are set up for the qualitative risk assessment such as the HAZOP study. The natural gas leakage at the gas supply pipe is identified as the highest risk among the hazards identified through the HAZOP study and as a safety instrumented function the shutdown function for leakage was defined. SIL 2 and PFD($2.5{\cdot}10^{-3}$) for the shutdown function are determined by the layer of protection analysis(LOPA). The shutdown system(SIS) carrying out the shutdown function(SIF) is verified and designed according to qualitative and quantitative requirements of IEC 61508 and IEC 61511. As a result of SIL verification and SIS conceptual design, the shutdown system is composed of two gas detectors voted 1oo2, one programmable logic solver, and two shutdown valve voted 1oo2.

A Study on the Reliability/Safety assessment and improvement of USN Gateway for Train Control (열차제어를 위한 USN Gateway 신뢰성, 안전성 평가 및 향상에 관한 연구)

  • Sin, Duc-Ko;Jo, Hyun-Jeong;Shin, Kyeng-Ho;Song, Yong-Soo
    • Journal of the Korean Society for Railway
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    • v.14 no.5
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    • pp.416-424
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    • 2011
  • The recent development of USN (Ubiquitous Sensor Network) technology has broadened its applications to many fields of industry. The USN technology enables the system to monitor and control the status of distributed sensor nodes based on the low-powered communications. Applying the USN in the train control domain, the operational efficiency can be enhanced, where the reliability and the safety of the system are the key challenges. This paper suggests the system design for evaluating and improving the reliability and safety of the gateway, which is a USN component that manages the radio network among the sensors and collects the information from them. For this purpose, the reliability and the level of safety integrity of a general gateway have been predicted quantitatively and the supplementary design has been proposed for the selected week points. The verification on the reliability and the safety of the improved gateway according to the related standards has been followed. With the results of the study, the applicability of USN gateway for train control systems has been reviewed.

The Classification Plan on Safety Certification System of Temporary Equipment (건설 가설재의 안전인증 분류방안)

  • Park, Sang-Wook;Park, Jun-Mo;Kim, Ok-Kyue
    • Proceedings of the Korean Institute Of Construction Engineering and Management
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    • 2008.11a
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    • pp.794-799
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    • 2008
  • At the point of changing from the capacity qualification of temporary equipments for building to safety certification system, the meaning of qualification and the present state of main products are evaluated for Capacity qualification system and compare with related system in developed country. These suggest classification of temporary equipments for building construction in safety certification. Now, present state of the capacity qualification system is estimated; according to the reforming system from restating law in 2003, there are a lot of changing of application in every 3 years because of that. The ability of Making business is improved by checking again but, there are limitation to constantly keep the safety as the system to approve form about sent imitation products. Changing from the capacity qualification system to safely certification system make to include the structure of the qualification system and make a plan standard. It make least panic in the building market and set up some standards for capacity by changing building circumstance. The classification of temporary equipment for building construction in safety certification from the module of quotation form classify each duty quotation item, self-regulation safely verification item and option quotation item, these will more improve the system form and quality of temporary equipment for building than before.

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Development of an Accident Consequence Assessment Code for Evaluating Site Suitability of Light- and Heavy-water Reactors Based on the Korean Technical Standards

  • Hwang, Won Tae;Jeong, Hae Sun;Jeong, Hyo Joon;Kil, A Reum;Kim, Eun Han;Han, Moon Hee
    • Journal of Radiation Protection and Research
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    • v.41 no.4
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    • pp.368-372
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    • 2016
  • Background: Methodologies for a series of radiological consequence assessments show a distinctive difference according to the design principles of the original nuclear suppliers and their technical standards to be imposed. This is due to the uncertainties of the accidental source term, radionuclide behavior in the environment, and subsequent radiological dose. Both types of PWR and PHWR are operated in Korea. However, technical standards for evaluating atmospheric dispersion have been enacted based on the U.S. NRC's positions regardless of the reactor types. For this reason, it might cause a controversy between the licensor and licensee of a nuclear power plant. Materials and Methods: It was modelled under the framework of the NRC Regulatory Guide 1.145 for light-water reactors, reflecting the features of heavy-water reactors as specified in the Canadian National Standard and the modelling features in MACCS2, such as atmospheric diffusion coefficient, ground deposition, surface roughness, radioactive plume depletion, and exposure from ground deposition. Results and Discussion: An integrated accident consequence assessment code, ACCESS (Accident Consequence Assessment Code for Evaluating Site Suitability), was developed by taking into account the unique regulatory positions for reactor types under the framework of the current Korean technical standards. Field tracer experiments and hand calculations have been carried out for validation and verification of the models. Conclusion: The modelling approaches of ACCESS and its features are introduced, and its applicative results for a hypothetical accidental scenario are comprehensively discussed. In an applicative study, the predicted results by the light-water reactor assessment model were higher than those by other models in terms of total doses.

Study on the Development and the Effects of a Fire Safety Education Program for the Elderly (노인을 위한 소방안전교육 프로그램 개발 및 효과분석)

  • Kim, Youngdo;Kim, Youngbin
    • Fire Science and Engineering
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    • v.32 no.3
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    • pp.123-133
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    • 2018
  • This study analyzed the effects influencing the elderly's knowledge on fire safety and practices of fire safety accident prevention after developing a Fire Safety Education Program for the elderly. The program was developed through verification using some experts and a pilot study after selecting the objective, goals, contents, and teaching & learning methods of the program based on the basic survey and literature review. The effects of the program were verified by conducting some non-equivalent control group pre- and post-tests after dividing the targets into the experimental group (the Fire Safety Education Program for the elderly was implemented) and control group (only printed hand-outs were given) among 48 elderly people no younger than 65 years of age. A paired t-test revealed some statistically significant differences between the scores of the pre- and post-tests of the experimental and control groups. ANCOVA found that the effects of the program were significantly higher than those of the printed hand-outs because the post-test scores of the experimental group were higher than those of the control group.

ASSESSMENT OF CFD CODES USED IN NUCLEAR REACTOR SAFETY SIMULATIONS

  • Smith, Brian L.
    • Nuclear Engineering and Technology
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    • v.42 no.4
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    • pp.339-364
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    • 2010
  • Following a joint OECD/NEA-IAEA-sponsored meeting to define the current role and future perspectives of the application of Computational Fluid Dynamics (CFD) to nuclear reactor safety problems, three Writing Groups were created, under the auspices of the NEA working group WGAMA, to produce state-of-the-art reports on different aspects of the subject. The work of the second group, WG2, was to document the existing assessment databases for CFD simulation in the context of Nuclear Reactor Safety (NRS) analysis, to gain a measure of the degree of quality and trust in CFD as a numerical analysis tool, and to take initiatives to extend the existing databases. The group worked over the period of 2003-2007 and produced a final state-of-the-art report. The present paper summarises the material gathered during the study, illustrating the points with a few highlights. A total of 22 safety issues were identified for which the application of CFD was considered to potentially bring real benefits in terms of better understanding and increased safety. A list of the existing databases was drawn up and synthesised, both from the nuclear area and from other parallel, non-nuclear, industrial activities. The gaps in the technology base were also identified and discussed. In order to initiate new ways of bringing experimentalists and numerical analysts together, an international workshop -- CFD4NRS (the first in a series) -- was organised, a new blind benchmark activity was set up based on turbulent mixing in T-junctions, and a Wiki-type web portal was created to offer online access to the material put together by the group giving the reader the opportunity to update and extend the contents to keep the information source topical and dynamic.

The Effect of Authentic Leadership on Creativity: the Multiple Mediating Effection of Psychological Safety and Cooperation Behavior (진성리더십이 창의성에 미치는 영향: 심리적 안전과 협력행동의 다중매개효과)

  • Choi, Woo-Su;Oh, Sang-Jin
    • The Journal of the Korea Contents Association
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    • v.21 no.1
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    • pp.485-497
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    • 2021
  • The purpose of this study is to demonstrate the effects of authentic leadership on creativity, psychological safety, and the mediating effects of cooperative behavior in order to enhance the creativity of personnel as a means of innovation in enterprises. The hypothesis was established based on the theory and prior study of authentic leadership, creativity, psychological safety, cooperation behavior. The data collected from 353 employees of domestic enterprises were verified for reliability and validity through CFA, SPSS 25, and AMOS 25. Macro Process 3.0 was used for hypothesis testing. Verification of the hypothesis of the study model showed that authentic leadership had a significant positive effect on psychological safety, cooperation behavior and creativity, and that the mediating effect of psychological safety and cooperation behavior was also significant. The significance of this study can be found in the fact that the impact of authentic leadership has been verified based on motivation among the CMC (Componential Model of Creativity) and that it has suggested that creativity of an organization's personnel may be enhanced by changing organizational culture through leadership.

Human Error Probability Determination in Blasting Process of Ore Mine Using a Hybrid of HEART and Best-Worst Methods

  • Aliabadi, Mostafa Mirzaei;Mohammadfam, Iraj;Soltanian, Ali Reza;Najafi, Kamran
    • Safety and Health at Work
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    • v.13 no.3
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    • pp.326-335
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    • 2022
  • Background: One of the important actions for enhancing human reliability in any industry is assessing human error probability (HEP). The HEART technique is a robust tool for calculating HEP in various industries. The traditional HEART has some weaknesses due to expert judgment. For these reasons, a hybrid model is presented in this study to integrate HEART with Best-Worst Method. Materials Method: In this study, the blasting process in an iron ore mine was investigated as a case study. The proposed HEART-BWM was used to increase the sensitivity of APOA calculation. Then the HEP was calculated using conventional HEART formula. A consistency ratio was calculated using BWM. Finally, for verification of the HEART-BWM, HEP calculation was done by traditional HEART and HEART-BWM. Results: In the view of determined HEPs, the results showed that the mean of HEP in the blasting of the iron ore process was 2.57E-01. Checking the full blast of all the holes after the blasting sub-task was the most dangerous task due to the highest HEP value, and it was found 9.646E-01. On the other side, obtaining a permit to receive and transport materials was the most reliable task, and the HEP was 8.54E-04. Conclusion: The results showed a good consistency for the proposed technique. Comparing the two techniques confirmed that the BWM makes the traditional HEART faster and more reliable by performing the basic comparisons.

LUAV Software Certification Method using Checklists based on DO-178C (DO-178C 기반 체크리스트를 활용한 무인동력비행장치 소프트웨어 인증 방안)

  • Ji-Hun Kwon;Dong-Min Lee;Kyung-Min Park;Eun-Hee Lee;Sauk-Hoon Im;Yong-Hun Choi;Jong-Whoa Na
    • Journal of Aerospace System Engineering
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    • v.17 no.1
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    • pp.33-41
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    • 2023
  • As seen in the case of the Boeing 737 Max accident, the proportion of aircraft software is rapidly increasing. However, it is vulnerable to safety issues. In case of domestic aircraft software, to operate a Light Unmanned Aerial Vehicle (LUAV) less than an empty weight of 150 kg, safety certification is required for an Ultra-Light Vehicle (ULV). However, software certification procedure is not included. Since the use of LUAVs has increased recently, software verification is required. This paper proposed a checklist of LUAV software that could be applied to LUAV referring DO-178C, an aviation software certification standard. A case study of applying the proposed checklist to the Model-based Development-based Helicopter Flight Control Computer (FCC) project currently used by domestic and foreign advanced companies and institutions was conducted.