An evaluation of the effect of radiation environment on Linde 80 reactor vessel welds

被引:0
|
作者
DeVan, MJ [1 ]
Pavinich, WA [1 ]
机构
[1] Framatome Technol Inc, Lynchburg, VA 24506 USA
关键词
submerged-arc welds; reactor vessel; radiation embrittlement; irradiation temperature;
D O I
10.1520/STP10539S
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The B&W Owners Group (B&WOG) developed the Master Integrated Reactor Vessel Surveillance Program (MIRVP) to encompass all domestic operating pressurized water reactors (PWRs) with reactor vessels that contain Linde 80 submerged-arc welds. These PWRs include the reactor vessels fabricated by Babcock & Wilcox (B&W) that include B&W-designed 177-Fuel Assembly (FA) plants and Westinghouse-designed plants. The B&WOG Reactor Vessel Working Group has sponsored studies over the past several years to develop an understanding of the mechanisms and trends of radiation embrittlement for reactor vessel submerged-arc welds fabricated using Linde 80 weld flux. As part of the MIRVP, a Westinghouse-designed capsule was included to provide a comparison of irradiation data in the Westinghouse neutronic environment with the B&W 177-FA environment, This paper presents the effect of irradiation environment on the embrittlement trends of Linde 80 submerged-are welds based on mechanical test data available through the B&WOG and the literature, and existing trend curves.
引用
收藏
页码:291 / 301
页数:11
相关论文
共 50 条
  • [21] EVALUATION ON CONSTRAINT EFFECT OF REACTOR PRESSURE VESSEL UNDER PRESSURIZED THERMAL SHOCK
    Ogawa, Naoki
    Yoshimoto, Kentaro
    Hirota, Takatoshi
    Sakaguchi, Shohei
    Oumaya, Toru
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2013, VOL 1B: CODES AND STANDARDS, 2014,
  • [22] EVALUATION OF THE J INTEGRAL AND THE CLADDING EFFECT OF A CRACK IN THE REACTOR PRESSURE VESSEL.
    Kikuchi, Masanori
    Miyamoto, Hiroshi
    Sugawara, Satoshi
    Bulletin of the JSME, 1986, 29 (258): : 4026 - 4030
  • [23] ANALYTIC PREDICTIONS OF THE ANNEALING RESPONSE OF A533-B REACTOR VESSEL STEEL WELDS
    MAIN, AP
    SHRIVER, BL
    NUCLEAR TECHNOLOGY, 1982, 59 (03) : 456 - 462
  • [24] Radiation resistance of a nickel alloying reactor vessel steel
    RNTs 'Kurchatovskij Inst', Moscow, Russia
    At Energ, 1 (33-36):
  • [25] EXPERIMENTAL CHARACTERIZATION OF INCLUSIONS AND IMPURITIES IN PLATES AND WELDS OF REACTOR PRESSURE-VESSEL STEELS
    DEHODGINS, OC
    SHRIVER, BL
    JOURNAL OF METALS, 1982, 34 (08): : 49 - 49
  • [26] RADIATION PROTECTION EXPERIENCE WITH NRX REACTOR VESSEL CHANGE
    MACNEIL, JA
    AMERICAN INDUSTRIAL HYGIENE ASSOCIATION JOURNAL, 1971, 32 (05): : 11 - &
  • [27] SAFETY EVALUATION OF REACTOR VESSEL NOZZLE CRACKS
    RICCARDELLA, PC
    COOPER, WE
    MECHANICAL ENGINEERING, 1978, 100 (11) : 122 - 122
  • [28] Evaluation of in-vessel corium retention through external reactor vessel cooling for small integral reactor
    Park, Rae-Joon
    Lee, Jae Ryong
    Ha, Kwang Soon
    Kim, Hwan Yeol
    NUCLEAR ENGINEERING AND DESIGN, 2013, 262 : 571 - 578
  • [29] OBSERVATIONS OF A STEADY-STATE EFFECT LIMITING RADIATION-DAMAGE IN REACTOR VESSEL STEELS
    YANICHKO, SE
    CHIRIGOS, JN
    NUCLEAR ENGINEERING AND DESIGN, 1980, 56 (02) : 297 - 307
  • [30] Residual stresses evaluation in welds and implications for design for pressure vessel applications
    Price, John W. H.
    Pardowska, Anna M.
    Ibrahim, Raafat
    Finlayson, Trevor R.
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2006, 128 (04): : 638 - 643