Hydrogen embrittlement on fracture resistance of low-alloy reactor pressure vessel steel with high dynamic strain aging at 288 °C-Reference-Cited by-同舟云学术

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Hydrogen embrittlement on fracture resistance of low-alloy reactor pressure vessel steel with high dynamic strain aging at 288 °C

Published:2022-02 Issue: Volume:308 Page:131269
ISSN:0167-577X
Container-title:Materials Letters
language:en
Short-container-title:Materials Letters

Author:

Que Z.,Seifert H.P.,Mazánová V.,Spätig P.

Funder

Ministerstvo Školství, Mládeže a Tělovýchovy

Paul Scherrer Institut

Eidgenössisches Nuklearsicherheitsinspektorat

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,General Materials Science

Reference14 articles.

1. Hydrogen embrittlement of ASTM A 203 D nuclear structural steel

2. Role of hydrogen on the incipient crack tip deformation behavior in α-Fe: An atomistic perspective

3. Effects of strain rate and temperature on tensile behavior of hydrogen-charged SA508 Cl.3 pressure vessel steel

4. Effects of Hydrogen on Tensile Properties of SA508 Cl.3 Reactor Pressure Vessel Steel at High Temperature

5. Effect of dynamic strain ageing on environmental degradation of fracture resistance of low-alloy RPV steels in high-temperature water environments

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Study of cracking and microstructure in Co-free valve seat hardfacing;Nuclear Materials and Energy;2022-06

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