• Title/Summary/Keyword: Safety Integrity

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Regional Integrity Analysis using modernized GPS, Galileo and SBAS

  • Han, Sang-Sul;Shin, Dae-Sik;Cho, Jong-Chul;Park, Chan-Sik;Jun, Hyang-Sik;Nam, Gi-Wook;Lee, Sang-Jeong
    • Proceedings of the Korean Institute of Navigation and Port Research Conference
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    • v.1
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    • pp.417-421
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    • 2006
  • ICAO defines performance requirements of navigation system such as accuracy, integrity, continuity and availability. The integrity is most significant performance requirement in aviation where safety of life is crucial. Many researches on this topic anticipate that GPS with SBAS or Galileo can meet APV requirements and GPS with GBAS or Galileo with GBAS will meet CAT II and III requirements. These performance expectations are based on global analysis. In this paper regional integrity analysis in Korea using various combinations of modernized GPS, Galileo and SBAS is given. The simulation results show that CAT I requirement can be met using modernized GPS and Galileo alone, however, CAT II and III are not met even augmenting SBAS because of VPL. A more efficient augmentation such as GBAS which can reduce VPL dramatically is required to meet CAT II and III in Korean region.

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Experimental Evaluation of the Thermal Integrity of a Large Capacity Pressurized Heavy Water Reactor Transport Cask

  • Bang, Kyoung-Sik;Yang, Yun-Young;Choi, Woo-Seok
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.20 no.3
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    • pp.357-364
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    • 2022
  • The safety of a KTC-360 transport cask, a large-capacity pressurized heavy-water reactor transport cask that transports CANDU spent nuclear fuel discharged from the reactor after burning in a pressurized heavy-water reactor, must be demonstrated under the normal transport and accident conditions specified under transport cask regulations. To confirm the thermal integrity of this cask under normal transport and accident conditions, high-temperature and fire tests were performed using a one-third slice model of an actual KTC-360 cask. The results revealed that the surface temperature of the cask was 62℃, indicating that such casks must be transported separately. The highest temperature of the CANDU spent nuclear fuel was predicted to be lower than the melting temperature of Zircaloy-4, which was the sheath material used. Therefore, if normal operating conditions are applied, the thermal integrity of a KTC-360 cask can be maintained under normal transport conditions. The fire test revealed that the maximum temperatures of the structural materials, stainless steel, and carbon steel were 446℃ lower than the permitted maximum temperatures, proving the thermal integrity of the cask under fire accident conditions.

Effects on Unplanned Extubation, Oral Mucosa, and Facial Skin Integrity of New Method to Secure Endotracheal Tube (새로운 기관튜브 고정기구 적용이 비계획적 발관과 구강·안면 피부 통합성에 미치는 효과)

  • Kim, Jung Sook;Lee, Eun Sook;Park, Jin Hyang
    • Journal of Korean Clinical Nursing Research
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    • v.15 no.3
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    • pp.49-59
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    • 2009
  • Purpose: Examination was done of the effects on unplanned extubation, oral mucosa, and facial skin integrity in patients with oral intubation secured with a new method using Multifix Endo II. Methods: A prospective quasai-experimental design was used. Data were collected during a 3-week EICU admission period between Jun. 1 and Nov. 30. Two hundreds seventeen (conventional taping group: 105, Multifix Endo II group: 112) orally intubated adults were enrolled in the study at the EICU of the C University Hospital. Results: The incidence of unplanned extubation (${\chi}^2=11.580$, p=0.03) and scores for the facial skin integrity impairment of the Mutifix Endo II group (t=5.28, p=.000) were significantly lower than those of the conventional taping group even though the scores for oral mucosa impairment were not different. The nurse's evaluation of the clinical effectiveness of the two methods including convenience, comfort, safety, and satisfaction were also higher for the new securement method compared to the conventional taping group. Conclusion: The securement method using Mutifix Endo II was more effective than the conventional method in the prevention of unplanned extubation and maintenance facial skin integrity.

Evaluation of Occupant Protection of Van and Light Truck Vehicle (승합 및 경트럭의 탑승자 보호성능 평가)

  • Kim, Guan-Hee;Park, In-Song
    • Transactions of the Korean Society of Automotive Engineers
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    • v.20 no.3
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    • pp.13-19
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    • 2012
  • The fatalities rate for passenger vehicles, vans, and commercial vehicles is 1.23, 1.90 and 2.46 deaths per 10,000 registered vehicles, respectively. This shows that vans and commercial vehicles are vulnerable compare to passenger vehicles. To evaluate the crashworthiness of van and Light Truck Vehicle(LTV), we carried out frontal offset crash test at 64km/h, 40% overlap as per IIHS(Insurance Institute for Highway Safety). The test result show that LTV is very poor to protect occupant at frontal crash cause there is no safety system such as airbag and pretensioner and front end length(distance from front bumper to steering wheel) is short. One of the van rated as the lowest rating even it is equipped with airbag, cause its safety cage was collapsed during the test. This result shows that the structural integrity is very important in terms of occupant protection.

Numerical Modelling of Radionuclide Migration for the Underground Silo at Near-Field

  • Myunggoo Kang;Jaechul Ha
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.21 no.4
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    • pp.465-479
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    • 2023
  • To ensure the safety of disposal facilities for radioactive waste, it is essential to quantitatively evaluate the performance of the waste disposal facilities by using safety assessment models. This paper addresses the development of the safety assessment model for the underground silo of Wolseong Low-and Immediate-Level Waste (LILW) disposal facility in Korea. As the simulated result, the nuclides diffused from the waste were kept inside the silo without the leakage of those while the integrity of the concrete is maintained. After the degradation of concrete, radionuclides migrate in the same direction as the groundwater flow by mainly advection mechanism. The release of radionuclides has a positive linear relationship with a half-life in the range of medium half-life. Additionally, the solidified waste form delays and reduces the migration of radionuclides through the interaction between the nuclides and the solidified medium. Herein, the phenomenon of this delay was implemented with the mass transfer coefficient of the flux node at numerical modeling. The solidification effects, which are delaying and reducing the leakage of nuclides, were maintained the integrity of the nuclides. This effect was decreased by increasing the half-life and the mass transfer coefficient of radionuclides.

Design and Characteristics of cryogenic ball valve (초저온 볼 밸브 설계 및 특성)

  • Kim, Dong-Soo;Kim, Myoung-Sub
    • Proceedings of the KSME Conference
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    • 2007.05a
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    • pp.666-671
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    • 2007
  • To acquire the safety along with durability of mechanical machinery products, we should consider the structural mechanics such as stress, deformation and dynamic vibration characteristics and identify those important aspects in the stage of preliminary design engineering. This cryogenic ball valve is used to transfer the liquified natural gas which temperature is $-196^{\circ}C$, supplied pressure is $168kg/cm^2$. For the cryogenic ball valve, the assurance of structural integrity and operability are essential to meet not only normal, abnormal loading conditions but also functionality during a seismic event. In this thesis, analytical approach and results using finite element analysis and computational method are herein presented to evaluate the aspects of structural integrity along with operability of cryogenic ball valve. In this study, we designed the high pressure cryogenic ball valve that accomplishes zero leakage by elastic seal at normal temperature and metal seal at high temperature.

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The integrity assessment of the pipeline (파이프라인의 건전성 평가)

  • 이억섭;황인현
    • Proceedings of the Korean Institute of Industrial Safety Conference
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    • 2000.06a
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    • pp.25-30
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    • 2000
  • The object of this work is to develop an assessment system for pipeline integrity The system consists of four module applications for internal algorithm; the effect of corrosion in pipeline, crack, stress corrosion crack (SCC) and fatigue modules. Presently, the module of the external corrosion has been developed and the internal algorithm for the effect of corrosion in pipeline and the database of the system are described in this paper, The database of the system is separated to mainly four parts; geometry of pipeline, material properties, boundary conditions and general Properties. Each components of the system are designed by user-friendly concept. This system may give a guideline for maintenance and modifications for the pipeline at the industrial sight. Furthermore, a procedure to evaluate an inspection interval is also provided.

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Effect of Finite Element Model on the Integrity Evaluation of Nuclear Piping (유한요소 해석모델이 원자력 배관의 건전성 평가에 미치는 영향)

  • Huh, Nam-Su;Kim, Young-Jin;Pyo, Chang-Ryul;Yu, Young-Jin
    • Journal of the Korean Society of Safety
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    • v.15 no.2
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    • pp.51-58
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    • 2000
  • Recently, the J/T analysis based on elastic-plastic finite element analysis is popularly used in the nuclear industry to assess the integrity of a cracked pipe. The objective of this paper is to evaluate the effect of stress-strain curve for weld metal, variation of crack incremental length(${\delta}a$), and crack face pressure on the J/T analysis result. For this purpose, a parametric analysis was performed and the results calculated from finite element analysis were compared with those from the piping experimental data(stainless steel weldment pipe with circumferential through-wall crack). The numerical result using base metal material property is in agreement with the experimental one and the maximum load is decreased as the ${\delta}a$ for J/T analysis is increased.

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A study on the Relations Between Fracture Strain and Fracture Resistance Curve of nuclear Pressure Vessel Steel (압력용기강의 파괴저항곡선의 파괴변형률에 관한 연구)

  • 임만배
    • Journal of Ocean Engineering and Technology
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    • v.14 no.1
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    • pp.44-51
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    • 2000
  • Safety and integrity are required for reactor pressure vessels because they are operated in high temperature. There are single specimen method multiple specimen method and load ratio analysis method which used as evaluation of safety and integrity for reactor pressure vessels. In this study the fracture resistance curve(J-R curve) elastic-plastic fracture toughness($J_{IC}$) and material tearing modulus ($T_{mat}$) of SA 508 class 3 alloy steel used as reactor pressure vessel steel are measured and evaluated at room temperature 20$0^{\circ}C$ and 30$0^{\circ}C$ according to unloading compliance method and load ration analysis method. And then the comparison with experimental $J_{IC}$ and theoretical$J_{IC}$ by local fracture strain is managed.

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