Irradiation Creep Behavior of High‐Purity Stainless Steels and Ni‐Base‐Alloys

Garzarolli, F.; Dewes, P.; Trapp-Pritsching, S.; Nelson, J.L.

doi:10.1002/9781118787618.ch107

Cited by 4 publications

(4 citation statements)

References 9 publications

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“…Irradiation-induced microstructural and microchemical changes, along with the change in water chemistry, are responsible for the occurrence of IASCC. A sharp rise in cracking susceptibility has been observed above a dose of 0.75 dpa in boiling water reactors [172], and 3 dpa in pressurized water reactors [173]. Because of the complex nature of the multivariate dependence, a clear dose threshold for IASCC may not exist.…”

Section: Corrosion and Irradiation-assisted Stress Corrosion Crackingmentioning

confidence: 99%

Promoting the Regulatory Acceptance of Combined Ion and Neutron Irradiation for Material Degradation in Nuclear Reactors

Jokisaari,

Chen,

Chen

et al. 2023

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Section: Corrosion and Irradiation-assisted Stress Corrosion Crackingmentioning

confidence: 99%

Promoting the Regulatory Acceptance of Combined Ion and Neutron Irradiation for Material Degradation in Nuclear Reactors

Jokisaari,

Chen,

Chen

et al. 2023

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“…However, stress relaxation by irradiation creep can be beneficial in cases where the reduction of high stresses at the crack tips helps to mitigate stress corrosion cracking (SCC) in the case of austenitic steels and Ni-alloys [ 14 ] or delayed hydride cracking (DHC) for Zr-alloys [ 15 , 16 ]. With respect to SCC, Garzarolli showed that, whereas higher creep rates are beneficial in blunting cracks, they do not account for the relative propensity for the SCC of austenitic alloys [ 17 ]. High stress irradiation creep at the crack tips is important for flaw disposition in Zr-alloy components that are prone to delayed hydride cracking.…”

Section: Introductionmentioning

confidence: 99%

Microstructural Effects on Irradiation Creep of Reactor Core Materials

Griffiths

2023

Materials

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The processes that control irradiation creep are dependent on the temperature and the rate of production of freely migrating point defects, affecting both the microstructure and the mechanisms of mass transport. Because of the experimental difficulties in studying irradiation creep, many different hypothetical models have been developed that either favour a dislocation slip or a mass transport mechanism. Irradiation creep mechanisms and models that are dependent on the microstructure, which are either fully or partially mechanistic in nature, are described and discussed in terms of their ability to account for the in-reactor creep behaviour of various nuclear reactor core materials. A rate theory model for creep of Zr-2.5Nb pressure tubing in CANDU reactors incorporating the as-fabricated microstructure has been developed that gives good agreement with measurements for tubes manufactured by different fabrication routes having very different microstructures. One can therefore conclude that for Zr-alloys at temperatures < 300 °C and stresses < 150 MPa, diffusional mass transport is the dominant creep mechanism. The most important microstructural parameter controlling irradiation creep for these conditions is the grain structure. Austenitic alloys follow similar microstructural dependencies as Zr-alloys, but up to higher temperature and stress ranges. The exception is that dislocation slip is dominant in austenitic alloys at temperatures < 100 °C because there are few barriers to dislocation slip at these low temperatures, which is linked to the enhanced recombination of irradiation-induced point defects.

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“…Creviced specimens were a novel development by Silverman and Taylor. 7 Finally, a slowly expanding core mandrill test was devised 8 to simulate and allow testing of nuclear fuel canning under realistic stressing conditions. This paper aims to describe and review some developments in and diverse applications of slow strain rate testing the present author has been associated with over a 43 year period, which started at Newcastle and was principally associated with the nuclear industry and steam generators in particular.…”

Section: Introductionmentioning

confidence: 99%

“…Creviced specimens were a novel development by Silverman and Taylor 7. Finally, a slowly expanding core mandrill test was devised8 to simulate and allow testing of nuclear fuel canning under realistic stressing conditions.…”

Section: Introductionmentioning

confidence: 99%

Some developments in slow strain rate testing for stress corrosion cracking

Poulson

2012

Corrosion Engineering, Science and Technology

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Several developments and novel applications of slow strain rate testing for stress corrosion cracking are described. Included are on site plant use, increasing pressure tests, component and hollow tensile specimens, and the incorporation of heat transfer effects into a specimen suitable for high pressure, high temperature applications. The application of slow strain rate testing, its advantages, disadvantages and some recent criticisms are also reviewed, together with its use as a tool for obtaining mechanistic insights.

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Irradiation Creep Behavior of High‐Purity Stainless Steels and Ni‐Base‐Alloys

Cited by 4 publications

References 9 publications

Promoting the Regulatory Acceptance of Combined Ion and Neutron Irradiation for Material Degradation in Nuclear Reactors

Promoting the Regulatory Acceptance of Combined Ion and Neutron Irradiation for Material Degradation in Nuclear Reactors

Microstructural Effects on Irradiation Creep of Reactor Core Materials

Some developments in slow strain rate testing for stress corrosion cracking

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