EFFECT OF HYDROGENATION ON THE FRACTURE MODE OF A REACTOR PRESSURE-VESSEL STEEL

被引:9
作者
Taylor, N. [2 ]
Nykyforchyn, H. M. [1 ]
Tsyrulnyk, O. T. [1 ]
Student, O. Z. [1 ]
机构
[1] Ukrainian Natl Acad Sci, Karpenko Physicomech Inst, Lvov, Ukraine
[2] European Commiss Joint Res Ctr, Inst Energy, Petten, Netherlands
关键词
reactor pressure-vessel steel; heat affecting zone under cladding; fracture toughness; subcritical crack growth; hydrogen embrittlement; intergranular fracture; INDUCED INTERGRANULAR FRACTURE;
D O I
10.1007/s11003-010-9223-2
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The conditions for hydrogen-induced intergranular fracture in an artificially embrittled, low-alloy reactor pressure-vessel steel were investigated by using fracture toughness and stress-corrosion cracking tests. The specimens were taken from two locations: the heat-affected zone beneath the cladding and the base material directly below the heat-affected zone. A hydrogenating system allowed the tests to be carried out on both prehydrogenated specimens and with continuous hydrogenation in the course of the tests. In total, the results demonstrate a detrimental effect of hydrogen on the subcritical crack-growth resistance of both materials. At 120 degrees C (close to the upper shelf), it led to a lower energy ductile fracture mode and isolated events of transgranular fracture. At ambient temperature (in the ductile-to-brittle transition mode) some mixed intergranular and transgranular subcritical crack growth was observed.
引用
收藏
页码:613 / 625
页数:13
相关论文
共 50 条
  • [31] Experimental evaluation of the size effect on the ductile and brittle fracture toughness of a steel pressure vessel
    Wang, Zhaoxi
    Shi, Huiji
    Lu, Jian
    ADVANCED MATERIALS SCIENCE AND TECHNOLOGY, 2009, 614 : 41 - 46
  • [32] Effects of neutron irradiation on resistivity of reactor pressure vessel steel
    Li, Chengliang
    Shu, Guogang
    Liu, Yi
    Huang, Yili
    Chen, Jun
    Duan, Yuangang
    Liu, Wei
    JOURNAL OF NUCLEAR MATERIALS, 2018, 499 : 446 - 450
  • [33] Characterization by notched and precracked Charpy tests of the in-service degradation of reactor pressure vessel steel fracture toughness
    Fabry, A
    SMALL SPECIMEN TEST TECHNIQUES, 1998, 1329 : 274 - 297
  • [34] Microstructure Evolution of a Reactor Pressure Vessel Steel During High-Temperature Tempering
    Li, Chuanwei
    Gu, Jianfeng
    Han, Lizhan
    Liu, Qingdong
    ENERGY MATERIALS 2017, 2017, : 317 - 326
  • [35] THE EFFECT OF A LOW CONSTRAINT GEOMETRY ON MEASURED To VALUES FOR A NUCLEAR REACTOR PRESSURE VESSEL FERRITIC STEEL
    Rait, Geena K.
    Davies, Catrin M.
    Garwood, Stephen J.
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2018, VOL 5, 2019,
  • [36] Effect of hydrogen on mechanical properties of heat affected zone of a reactor pressure vessel steel grade
    Rhode, Michael
    Steger, Joerg
    Steppan, Enrico
    Kannengiesser, Thomas
    WELDING IN THE WORLD, 2016, 60 (04) : 623 - 638
  • [37] Effect of hydrogen on mechanical properties of heat affected zone of a reactor pressure vessel steel grade
    Michael Rhode
    Joerg Steger
    Enrico Steppan
    Thomas Kannengiesser
    Welding in the World, 2016, 60 : 623 - 638
  • [38] Fracture mechanics properties of materials of reactor pressure vessel of WWER 440
    Lauerová, D
    Brumovsky, M
    ADVANCES IN MECHANICAL BEHAVIOUR, PLASTICITY AND DAMAGE, VOLS 1 AND 2, PROCEEDINGS, 2000, : 1499 - 1504
  • [39] Effect of minor rare earth cerium addition on the hot ductility of a reactor pressure vessel steel
    Guo, Yu
    Sun, Shufu
    Song, Shenhua
    RESULTS IN PHYSICS, 2019, 15
  • [40] A local approach incorporating the measured statistics of microcracks to assess the temperature dependence of cleavage fracture for a reactor pressure vessel steel
    Ruggieri, Claudio
    Jivkov, Andrey P.
    25TH INTERNATIONAL CONFERENCE ON FRACTURE AND STRUCTURAL INTEGRITY, 2019, 18 : 28 - 35