• 제목/요약/키워드: CFR

검색결과 160건 처리시간 0.023초

A Study on Effect of Risk Survey Using CATIA V5 Program for Loss Prevention

  • Kim, Tae-Gu;Lee, Sang-Hyun
    • International Journal of Safety
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    • 제5권1호
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    • pp.5-9
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    • 2006
  • The present study reports on the results of a risk survey of machinery safety at a shoe factory in Qingdao, China. The aim is to decrease industrial accidents and increase worker job satisfaction by searching for a change from a trend analysis and making improvements in problem areas. The first risk survey for machinery safety was carried out in April 2005. Based on the analysis of the survey results, machinery safety devices was installed in the factory by using CATlA V5. Also, we investigated job satisfaction concerning working apparatus and work tool improvement in a questionnaire about the working environment. The second survey of machinery safety was carried out in September 2005. We are in the process of comparing the first survey results with the second survey results in order to analyze decreasing trend in industrial accidents and improvement in job satisfaction. So far the data have shown improved short-term turnover and absenteeism. It means CATIVA V5 and CFR has had positive effect regarding safety in shoe manufacture industry. The survey with CATIVA V5 and CFR will be expanded to other East-Asian countries including Vietnam. The hope is that the present approach could make a significant contribution toward improved safety.

Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors

  • Yoon, Ji-Hyun;Lee, Bong-Sang
    • Nuclear Engineering and Technology
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    • 제49권5호
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    • pp.1109-1112
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    • 2017
  • The precise prediction of radiation embrittlement of aged reactor pressure vessels (RPVs) is a prerequisite for the long-term operation of nuclear power plants beyond their original design life. The expiration of the operation licenses for Korean reactors the RPVs of which are made from SA533B-1 plates and welds is imminent. Korean regulatory rules have adopted the US Nuclear Regulatory Commission's transition temperature shift (TTS) models to the prediction of the embrittlement of Korean reactor pressure vessels. The applicability of the TTS model to predict the embrittlement of Korean RPVs made of SA533B-1 plates and welds was investigated in this study. It was concluded that the TTS model of 10 CFR 50.61a matched the trends of the radiation embrittlement in the SA533B-1 plates and welds better than did that of Regulatory Guide (RG) 1.99 Rev. 2. This is attributed to the fact that the prediction performance of 10 CFR 50.61a was enhanced by considering the difference in radiation embrittlement sensitivity among the different types of RPV materials.

Assessing 3D seismic damage performance of a CFR dam considering various reservoir heights

  • Karalar, Memduh;Cavusli, Murat
    • Earthquakes and Structures
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    • 제16권2호
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    • pp.221-234
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    • 2019
  • Today, many important concrete face rockfill dams (CFRDs) have been built on the world, and some of these important structures are located on the strong seismic regions. In this reason, examination and monitoring of these water construction's seismic behaviour is very important for the safety and future of these dams. In this study, the nonlinear seismic behaviour of Ilısu CFR dam which was built in Turkey in 2017, is investigated for various reservoir water heights taking into account 1995 Kobe near-fault and far-fault ground motions. Three dimensional (3D) finite difference model of the dam is created using the FLAC3D software that is based on the finite difference method. The most suitable mesh range for the 3D model is chosen to achieve the realistic numerical results. Mohr-Coulomb nonlinear material model is used for the rockfill materials and foundation in the seismic analyses. Moreover, Drucker-Prager nonlinear material model is considered for the concrete slab to represent the nonlinearity of the concrete. The dam body, foundation and concrete slab constantly interact during the lifetime of the CFRDs. Therefore, the special interface elements are defined between the dam body-concrete slab and dam body-foundation due to represent the interaction condition in the 3D model. Free field boundary condition that was used rarely for the nonlinear seismic analyses, is considered for the lateral boundaries of the model. In addition, quiet artificial boundary condition that is special boundary condition for the rigid foundation in the earthquake analyses, is used for the bottom of the foundation. The hysteric damping coefficients are separately calculated for all of the materials. These special damping values is defined to the FLAC3D software using the special fish functions to capture the effects of the variation of the modulus and damping ratio with the dynamic shear-strain magnitude. Total 4 different reservoir water heights are taken into account in the seismic analyses. These water heights are empty reservoir, 50 m, 100 m and 130 m (full reservoir), respectively. In the nonlinear seismic analyses, near-fault and far-fault ground motions of 1995 Kobe earthquake are used. According to the numerical analyses, horizontal displacements, vertical displacements and principal stresses for 4 various reservoir water heights are evaluated in detail. Moreover, these results are compared for the near-fault and far-faults earthquakes. The nonlinear seismic analysis results indicate that as the reservoir height increases, the nonlinear seismic behaviour of the dam clearly changes. Each water height has different seismic effects on the earthquake behaviour of Ilısu CFR dam. In addition, it is obviously seen that near-fault earthquakes and far field earthquakes create different nonlinear seismic damages on the nonlinear earthquake behaviour of the dam.

전파 경로손실 예측 모델 (Prediction Models for the Path Loss in Mobile Communications)

  • 구본희;김채영;목진담
    • 전자통신동향분석
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    • 제11권2호통권40호
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    • pp.17-29
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    • 1996
  • 본 고에서는 이동통신 시스템의 전파특성을 이해하기 위해 800~950MHz 대역에 적용되는 전파경로손실 예측모델을 소개한다. 또한 미연방통신위원회(Federal Communications Commission; FCC)의 미연방통신법전(Code of Federal Regulations; CFR) Part 90에서 규정하고 있는 전계강도 기준을 전계강도 예측모델로서 분석해보고 그 타당성을 제시한다.

특수형방사성물질 봉인캡슐의 기술기준에 의한 안전성시험

  • 서기석;방경식;한현수;조운갑;민덕기;노성기
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1998년도 춘계학술발표회논문집(2)
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    • pp.691-696
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    • 1998
  • 원자력연구소의 연구용 원자로인 하나로(HAHARO)에서 생산되는 방사성동위원소인 Ir-192를 안전하게 운반하기 위해 특수형방사성물질 봉인캡슐을 제작하여 국내·외 수송관련법규인 과기처 고시 제 96-38호, IAEA Safety Series No. ST-1기 및 미국 10 CFR Part 71의 규정에 따라 원자력연구소내의 수송용기 안전성시험시설에서 특수협 방사성물질인 Ir-192 봉인캡슐에 대한 안전성시험분석을 수행하였다.

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Read-back Error 요인의 해석 (A Study of the interpretive rule on pilot's read-back error)

  • 신현삼
    • 한국항공운항학회지
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    • 제8권1호
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    • pp.111-124
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    • 2000
  • In this study, pilot's read-back errors were reviewed in terms of its cause and consequence while FAA tried to weigh a new initiative in the atc-pilot communication dispute in opposition of a majority of the aviation community by addressing an interpretive rule of 14CFR 91. Especially human factors in ATC communications were outlined with a view to suggest a line of recommendations for a successful accomplishment of safe flight in the busy terminal airspace.

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Mechanical Design of Deepwater Pipeline Wall Thickness Using the Recent Rules

  • Choi, Han-Suk
    • International Journal of Ocean Engineering and Technology Speciallssue:Selected Papers
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    • 제5권1호
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    • pp.58-63
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    • 2002
  • This paper presents a mechanical design of the deepwater pipeline wall thickness using the recent design rules. Characteristics and limitations of the new codes were identified through a case study design in the Gulf of Mexico. In addition to the ASME, API, and DVD codes, the code of federal regulations (CFR) was also utilized in the design. It was found that conservatism still exists within the collapse prediction for water depth greater than 1500 m. Comparision of the results from DNV and API codes were presented.

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미국 전동차 Manual bridge plate 에 대한 고찰 (Sturdy for the development of Bridge plate of SEPTA Sliver Line V)

  • 최세중;염경안
    • 한국철도학회:학술대회논문집
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    • 한국철도학회 2008년도 추계학술대회 논문집
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    • pp.451-457
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    • 2008
  • The aim of the sturdy is for the development of Bridge plate installing on floor for SETPA Sliver line V. SEPTA train have pocket sliding door which is similar with domestic trains. typically In the USA railway market, Portable type and standing type bridge plate used, easily hiding the bridge plate in stowed position and convenience operation, Bridge plate installed on floor is designed. relative regulation Like CFR APTA, and EN, UIC is reviewed and compared.

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경수로 사용후핵연료 건식 중간저장시설에 대한 예비 방사선 영향 평가 (Preliminary Assessment of Radiation Impact from Dry Storage Facilities for PWR Spent Fuel)

  • 김태만;백창열;차길용;이우교;김순영
    • Journal of Radiation Protection and Research
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    • 제37권4호
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    • pp.197-201
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    • 2012
  • 경수로 사용후핵연료 중간저장시설의 부지면적을 산출하기 위하여 콘크리트 저장시설 개념모델의 연간선량을 계산하였다. 초기농축도 4.5 wt%, 연소도 45,000 MWd/MTU, 냉각기간 10년인 사용후핵연료를 대상으로 ORIGEN-ARP를 사용하여 선원항을 생산하였으며, MCNP 코드를 사용하여 저장시설에 대한 모델링 및 방사선차폐계산을 수행하였다. 연간선량은 저장시설의 용량별로 계산하였으며, 중앙집중식 저장시설의 경우, 반경 700 m 이상에서 10CFR72에서 권고하는 통제구역 경계에서의 연간선량 기준 0.25 mSv를 만족하였다.