Master curve application to WWER reactor pressure vessels integrity

被引:0
|
作者
Brumovsky, Milan [1 ]
机构
[1] Nucl Res Inst Rez Plc, Rez 25068, Czech Republic
关键词
D O I
暂无
中图分类号
TU [建筑科学];
学科分类号
0813 ;
摘要
Lifetime of reactor pressure vessels is practically determined by their resistance against potential brittle/non-ductile failure. This resistance is then governs by the damaging effect of neutron embrittlement. Integrity assessment of reactor pressure vessels has been changed and improved during past several decades but still it contains some parameters that were introduced historically and still are being used. Representative of such parameters is Charpy notch impact testing and resulting transition temperature determination. Even though this test has technological origin, it is still used in material acceptance tests and also practically in most of surveillance specimens programmes for determination of radiation damage level. Vast application of fracture mechanics to reactor pressure vessels integrity assessment have brought also a tendency for finding a correlation between results of Charpy notch impact tests and fracture mechanics parameters - results are usually called,design fracture toughness curves". Contraversion between Charpy impact tests and fracture mechanics use for RPV integrity assessment can be overrun by direct use of static fracture toughness data obtained from surveillance, e.g. using a specimen reconstitution technique.
引用
收藏
页码:926 / 930
页数:5
相关论文
共 50 条
  • [31] ON ISSUE OF COMPARISON OF THE UNIFIED CURVE AND MASTER CURVE METHODS AND APPLICATION FOR RPV STRUCTURAL INTEGRITY ASSESSMENT
    Margolin, B. Z.
    Fomenko, V. N.
    Gulenko, A. G.
    Kostylev, V. I.
    Shvetsova, V. A.
    STRENGTH OF MATERIALS, 2016, 48 (02) : 227 - 250
  • [32] Integrated surveillance specimen program for WWER-1000/V-320 reactor pressure vessels
    Brumovsky, M.
    Brynda, J.
    Kytka, M.
    Novosad, P.
    Zd'arek, J.
    PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY, 2007, (02): : 97 - 100
  • [33] Structural integrity assessment of reactor pressure vessels during pressurized thermal shock
    Myung Jo Jhung
    Seok Hun Kim
    Young Hwan Choi
    Sunggyu Jung
    Jong Min Kim
    Ji Ho Kim
    Jong Wook Kim
    Changheui Jang
    Yoon Suk Chang
    Ki Sig Kang
    Journal of Mechanical Science and Technology, 2008, 22 : 1451 - 1459
  • [34] Integrity analysis of reactor pressure vessels subjected to pressurized thermal shocks by XFEM
    Gonzalez-Albuixech, V. F.
    Qian, G.
    Niffenegger, M.
    NUCLEAR ENGINEERING AND DESIGN, 2014, 275 : 336 - 343
  • [35] Probabilistic Structural Integrity Analysis of Reactor Pressure Vessels during PTS Events
    Onizawa, Kunio
    Masaki, Koichi
    Katsuyama, Jinya
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, PVP 2012, VOL 1, 2012, : 695 - 701
  • [36] Structural integrity assessment of reactor pressure vessels during pressurized thermal shock
    Jhung, Myung Jo
    Kim, Seok Hun
    Choi, Young Hwan
    Jung, Sunggyu
    Kim, Jong Min
    Kim, Ji Ho
    Kim, Jong Wook
    Jang, Changheui
    Chang, Yoon Suk
    Kang, Ki Sig
    JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY, 2008, 22 (08) : 1451 - 1459
  • [37] The influence of thermomechanical loading history on the stress level in WWER NPP reactor pressure vessels under thermal shock
    V. V. Kharchenko
    A. Yu. Chirkov
    S. V. Kobel’skii
    V. I. Kravchenko
    V. A. Piminov
    I. F. Akbashev
    Strength of Materials, 2010, 42 : 17 - 24
  • [38] THE INFLUENCE OF THERMOMECHANICAL LOADING HISTORY ON THE STRESS LEVEL IN WWER NPP REACTOR PRESSURE VESSELS UNDER THERMAL SHOCK
    Kharchenko, V. V.
    Chirkov, A. Yu.
    Kobel'skii, S. V.
    Kravchenko, V. I.
    Piminov, V. A.
    Akbashev, I. F.
    STRENGTH OF MATERIALS, 2010, 42 (01) : 17 - 24
  • [39] Implementation of results from MPA reactor safety research in the integrity assessment of German reactor pressure vessels
    Roos, E.
    Föhl, J.
    Nuclear Engineering and Design, 1999, 190 (01): : 97 - 115
  • [40] Implementation of results from MPA reactor safety research in the integrity assessment of German reactor pressure vessels
    Roos, E
    Föhl, J
    NUCLEAR ENGINEERING AND DESIGN, 1999, 190 (1-2) : 97 - 115