• Title/Summary/Keyword: EPRI

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A Numerical Study on Flow-Accelerated Corrosion in Two Adjacent Elbows

  • Yun, Hun;Hwang, Kyeongmo;Moon, Seung-Jae
    • Corrosion Science and Technology
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    • v.15 no.1
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    • pp.6-12
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    • 2016
  • Flow-Accelerated Corrosion (FAC) is a well-known degradation mechanism that attacks the secondary piping in nuclear power plants. Since the Surry Unit 2 event in 1986, most nuclear power plants have implemented management programs to deal with damages in carbon and low-alloy steel piping. Despite the utmost efforts, damage induced by FAC still occurs in power plants around the world. In order to predict FAC wear, some computer programs were developed such as CHECWORKS, CICERO, and COMSY. Various data need to be input to these programs; the chemical composition of secondary piping, flow operating conditions and piping geometries. CHECWORKS, developed by the Electric Power Research Institute (EPRI), uses a geometry code to calculate geometry effects. Such a relatively simple geometry code is limited in acquiring the accuracy of FAC prediction. Recently, EPRI revisited the geometry code with the intention of updating it. In this study, numerical simulations were performed for two adjacent $90^{\circ}$ elbows and the results were analysed in terms of the proximity effect between the two adjacent elbows.

신규 화재심각도 분류기준을 고려한 원전 화재발생빈도 추정

  • O, Hae-Cheol;Kim, Hyeong-Taek;Sin, Jeong-Min
    • Proceedings of the Korea Institute of Fire Science and Engineering Conference
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    • 2013.11a
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    • pp.191-192
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    • 2013
  • 원전 화재 PSA에서 화재 초기사건발생빈도는 전체 노심손상빈도에 직접 비례하여 영향을 주기 때문에 중요한 요소이다. 미국 NRC는 EPRI와의 공동연구를 통하여 원전 화재 PSA의 신규 방법론(NUREG/CR-6850)을 개발하였고, 미국 원전사업자들은 신규 방법론을 적용하여 화재 PSA를 수행하고 있다. 최근 EPRI는 원전 화재 초기사건 발생빈도 추정시 NUREG/CR-6850에서 사용된 화재심각도 분류방법을 개정한 지침서를 발간하였다. 본 논문에서는 신규 분류기준에 대해서 살펴보고, 국내 원전에서 경험한 화재사건에 대해서 신규 분류 기준을 적용하여 고찰하였다.

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Preliminary analyses on decontamination factors during pool scrubbing with bubble size distributions obtained from EPRI experiments

  • Lee, Yoonhee;Cho, Yong Jin;Ryu, Inchul
    • Nuclear Engineering and Technology
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    • v.53 no.2
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    • pp.509-521
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    • 2021
  • In this paper, from a review of the size distribution of the bubbles during pool scrubbing obtained from experiments by EPRI, we apply the bubble size distributions to analyses on the decontamination factors of pool scrubbing via I-COSTA (In-Containment Source Term Analysis). We perform sensitivity studies of the bubble size on the various mechanisms of deposition of aerosol particles in pool scrubbing. We also perform sensitivity studies on the size distributions of the bubbles depending on the diameters at the nozzle exit, the molecular weights of non-condensable gases in the carrier gases, and the steam fractions of the carrier gases. We then perform analyses of LACE-ESPANA experiments and compare the numerical ~ results to those from SPARC-90 and experimental results in order to show the effect of the bubble size distributions.

폐기물 연소 보일러의 튜브 손상 메카니즘

  • Baek, Se-Hyeon
    • 열병합발전
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    • s.68
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    • pp.9-13
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    • 2009
  • 최근 국내에 MSW(Municipal Solid Waste), RDF(Refuse-Derived Fuel) 또는 석탄과 폐기물을 혼합 연소하는 Waste-To-Energy 보일러 대한 관심이 증대되고 있는바, EPRI(Electric Power Research Institute)의 연구자료를 인용하여 상기 보일러에 대한 튜브 손상 메카니즘에 대하여 설명하고자 한다.

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해외동향

  • Korea Electrical Manufacturers Association
    • NEWSLETTER 전기공업
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    • no.98-23 s.216
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    • pp.18-30
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    • 1998
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Stress Indices of Hollow Circular Cross Section Welded Attachments on Piping Elbows with the Extended Parameters Range (매개변수 적용범위를 확장한 배관 곡관부에 용접 부착된 원형관 이음부의 이차응력지수)

  • Lee, Kun-Suk;Moon, Seong-Jae
    • Plant Journal
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    • v.15 no.4
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    • pp.43-51
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    • 2019
  • The stress concentration of the integral welded attachments (IWA) often used to support piping system has been a big issue because it induces local stresses in piping. The method to evaluate local stresses associated with attachments on elbows has been suggested in EPRI TR-107453. However, there are limitations regarding specific parameters range in order to use correlation equation. In this paper, parametric study based on piping elbow size and attachment dimension was performed utilizing finite element analysis (FEA) to evaluate the secondary stress indices of hollow circular cross section welded attachments on piping elbows with the extended parameters range. The results of the FEA were used to develop correlation formulas for calculating secondary stress indices. The empirical equations in this study are suggested as an alternative evaluation method of EPRI TR-107453 by extending parameters range.

Crack Opening Displacement Estimation for Engineering Leak-Before-Break Analyses of Pressurized Nuclear Piping (원자력 배관의 공학적 파단전누설 해석을 위한 균열열림변위 계산)

  • Huh Nam-Su;Kim Yun-Jae;Chang Yoon-Suk;Yang Jun-Seok;Choi Jae-Boons
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.28 no.10
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    • pp.1612-1620
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    • 2004
  • This study presents methods to estimate elastic-plastic crack opening displacement (COD) fur circumferential through-wall cracked pipes for the Leak-Before-Break (LBB) analysis of pressurized piping. Proposed methods are based not only on the GE/EPRI approach but also on the reference stress approach. For each approach, two different estimation schemes are given, one for the case when full stress-strain data are available and the other fur the case when only yield and ultimate tensile strengths are available. For the GE/EPRI approach a robust way of determining the Ramberg-Osgood (R-O) parameters is proposed, not only fur the case when detailed information on full stress-strain data is available but also for the case when only yield and ultimate tensile strengths are available. The COD estimates according to the GE/EPRI approach, using the R-O parameters determined from the proposed R-O fitting procedures, generally compare well with the published pipe test data. For the reference stress approach, the COD estimates according to the method based on both full stress-strain data and limited tensile properties are in good agreement with pipe test data. In conclusion, experimental validation given in the present study provides sufficient confidence in the use of the proposed method to practical LBB analyses even though when information on material's tensile properties is limited.

A Study on The Security Vulnerability Analysis of Open an Automatic Demand Response System (개방형 자동 수요 반응 시스템 보안 취약성 분석에 관한 연구)

  • Chae, Hyeon-Ho;Lee, June-Kyoung;Lee, Kyoung-Hak
    • Journal of Digital Convergence
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    • v.14 no.5
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    • pp.333-339
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    • 2016
  • Technology to optimize and utilize the use and supply of the electric power between consumer and supplier has been on the rise among the smart grid power market network in electric power demand management based on the Internet. Open Automated Demand Response system protocol, which can deliver Demand Response needed in electric power demand management to electricity supplier, system supplier and even the user is openADR 2.0b. This paper used the most credible, cosmopolitanly proliferated EPRI open source and analysed the variety of security vulnerability that developed VEN and VTN system may have. Using the simulator for attacking openADR protocol, the VEN/VTN system that has been implemented as EPRI open source was conducted to attack in a variety of ways. As a result of the analysis, we were able to get the results that the VEN/VTN system has security vulnerabilities to the parameter tampering attacks and service flow falsification attack. In conclusion, if you want to implement the openADR2.0b protocol system in the open or two-way communication environment smart grid network, considering a variety of security vulnerability should be sure to seek security technology and services.

Sampling-based Approach for Seismic Probabilistic Risk Assessment (지진 확률론적 리스크 평가를 위한 샘플링기반 접근법)

  • Kwag, Shinyoung;Eem, Seunghyun;Park, Junhee;Choi, In-Kil
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.33 no.2
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    • pp.129-136
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    • 2020
  • In this study, we develop a sampling-based seismic probabilistic risk assessment (SPRA) quantification technique that can accurately consider a partially dependent condition of component seismic fragility information. Specifically, the SPRA quantification method is proposed by combining the advantages of two representative methodologies: EPRI seismic fragility and JAERI seismic fragility input-based quantification. The most important feature of the proposed method is that it performs a SPRA using a sampling technique by transforming the EPRI seismic fragility input into JAERI seismic fragility input. When the proposed sampling-based approach was applied to an example of simple system and to a SPRA problem of a nuclear power plant, it was observed that the proposed method yields approximately similar system seismic fragility and seismic risk results as those of the exact solution. Therefore, it is believed that the approach proposed in this study can be used as a useful tool for accurately assessing seismic risks, considering the partial seismic dependence among the components; the existing SPRA method cannot handle such partial dependencies.