Application of advanced master curve approaches on WWER-440 reactor pressure vessel steels

被引:24
|
作者
Viehrig, Hans-Werner [1 ]
Scibetta, Marc [1 ]
Wallin, Kim [1 ]
机构
[1] CEN SCK, Reactor Mat Res, B-2400 Mol, Belgium
关键词
reactor pressure vessel steel; fracture toughness; master curve approach; inhomogeneous material; random inhomogeneity; maximum likelihood procedure; SINTAP procedure;
D O I
10.1016/j.ijpvp.2006.04.005
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The master curve (MC) approach used to measure the transition temperature, T-0, was standarised in the ASTM Standard Test Method E 1921 in 1997. The basic MC approach for analysis of fracture test results is intended for macroscopically homogeneous steels with a body centred cubic (ferritic) structure only. In reality, due to the manufacturing process, the steels in question are seldom fully macroscopically homogeneous. The fracture toughness values measured on Charpy size SE(B) specimens of base metal from the Greifswald Unit 8 rector pressure vessel (RPV) show large scatter. The basic MC evaluation following ASTM E1921 supplies a MC with many fracture toughness values which lie below the 5% fracture probability line. It is therefore suspected that this material is macroscopically inhomogeneous. In this paper, two recent extensions of the MC for inhomogeneous materials are applied to these fracture toughness data. (c) 2006 Elsevier Ltd. All rights reserved.
引用
收藏
页码:584 / 592
页数:9
相关论文
共 50 条
  • [41] Metallography methods application on the scoop samples from the reactor pressure vessels WWER-440 in Jaslovske Bohunice NPPV-1
    Kupca, L
    Brezina, M
    ANALYSIS OF IN-SERVICE FAILURES AND ADVANCES IN MICROSTRUCTURAL CHARACTERIZATION, 1999, 26 : 461 - 466
  • [42] Experimental and statistical analysis of radiation embrittlement (RE) of the WWER-440 vessel materials
    Nikolaeva, A.V.
    Nikolaev, Yu.A.
    Kevorkyan, Yu.P.
    Atomnaya Energiya, 2001, 90 (04): : 260 - 268
  • [43] Fracture mechanics characterisation of the beltline welding seam of the decommissioned WWER-440 reactor pressure vessel of nuclear power plant Greifswald Unit 4
    Viehrig, Hans-Werner
    Altstadt, Eberhard
    Houska, Mario
    Valo, Matti
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2012, 89 : 129 - 136
  • [44] Application of the Master Curve approach for the irradiation embrittlement evaluation of pressure vessel steels
    Viehrig, HW
    Böhmert, J
    STEEL RESEARCH INTERNATIONAL, 2003, 74 (09): : 577 - 583
  • [45] CHOICE OF METHOD OF TRANSPOSITION OF FUEL ASSEMBLIES DURING WWER-440 REACTOR REFUELING
    KOCHANOVSKAJA, LV
    KERNENERGIE, 1977, 20 (10): : 307 - 308
  • [46] ANALYSES OF THERMAL ANNEALING INFLUENCE ON WWER 440 REACTOR PRESSURE VESSEL INTERNALS MATERIALS
    Petelova, Petra
    Eliasova, Ivana
    Kopriva, Radim
    Bursik, Ondrej
    Tonarova, Dana
    Materna, Ales
    28TH INTERNATIONAL CONFERENCE ON METALLURGY AND MATERIALS (METAL 2019), 2019, : 787 - 792
  • [47] WARM PRE-STRESSING TESTS FOR WWER 440 REACTOR PRESSURE VESSEL MATERIAL
    Lauerova, Dana
    Pistora, Vladislav
    Brumovsky, Milan
    Kytka, Milos
    ASME PRESSURE VESSELS AND PIPING CONFERENCE 2009, VOL 3: DESIGN AND ANALYSIS, 2010, : 309 - 320
  • [48] Master Curve and Unified Curve applicability to highly neutron irradiated Western type reactor pressure vessel steels
    Zurbuchen, Conrad
    Viehrig, Hans-Werner
    Weiss, Frank-Peter
    NUCLEAR ENGINEERING AND DESIGN, 2009, 239 (07) : 1246 - 1253
  • [49] Actual properties of WWER-440 reactor pressure vessel materials obtained by impact tests of subsize specimens fabricated out of samples taken from the RPV
    ORM Russ. Res. Ctr. Kurchatov Inst., 123182 Moscow, Russia
    不详
    不详
    ASTM Spec Tech Publ, 1329 (145-159):
  • [50] APPLICATION OF MASTER CURVE APPROACH TO SURVEILLANCE TEST DATA FOR WWER-1000 REACTOR PRESSURE VESSELS
    Revka, Volodymyr M.
    Chyrko, Liudmyla I.
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2017, VOL 1A, 2017,