Yugo Ashida's research while affiliated with University of Michigan and other places
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Publications (10)
Mechanical properties such as yield strength and hardness of irradiated stainless steels can be significantly changed by increasing irradiation dose. An understanding of the effects of mechanical properties on crack growth in neutron-irradiated stainless steels is required for identifying the irradiation assisted stress corrosion cracking (IASCC) m...
This paper describes the development of both facilities and capabilities for conducting crack growth rate tests on neutronirradiated alloys in light water reactor (LWR) environments. The facilities consisting of hot cells and a high-temperature water corrosion test laboratory were developed to evaluate crack growth rates (CGR) of neutron-irradiated...
To better understand the mechanism of irradiation assisted stress corrosion cracking (IASCC) and to establish strategies for IASCC mitigation, crack growth data were obtained on neutron-irradiated stainless steels with various solute additions. The alloys include PS (316L+Hf, 9.6 dpa), IP (304 -C+P, 4.4 dpa), and MS (304+Ti, 10.7 dpa). The specimen...
This paper describes the facilities for conducting crack growth rate (CGR) tests on neutron-irradiated alloys in LWR environments. A set of procedures were developed for using the facilities to test CGRs of neutron-irradiated stainless steel in the Irradiated Materials Testing Complex (IMTC) at the University of Michigan. The DCPD technique was use...
To better understand the irradiation assisted stress corrosion cracking (IASCC) mechanism and to establish strategies for IASCC mitigation, it is essential to acquire accurate crack growth data on neutron-irradiated alloys in the relevant environment. In this study, a crack growth rate (CGR) test on a neutron-irradiated stainless steel alloy was co...
Irradiation-assisted stress corrosion cracking (IASCC) refers to the process(es) by which irradiation enhances the inherent susceptibility of alloys to stress corrosion cracking (SCC). This article begins with an introduction to the IASCC problem experienced in light water reactors, followed by a summary of existing plant and laboratory data that r...
IntroductionExperimentResultsDiscussionConclusions
Acknowledgements
The key factors affecting crack growth behavior of neutron irradiated stainless steel were investigated in this study. A crack growth rate (CGR) test was conducted under accurate constant K control on a neutron-irradiated 8 mm RCT specimen (9.6 dpa) of high purity 316L stainless steel with Hf addition in simulated BWR (NWC, HWC) and PWR environment...
The susceptibility of neutron irradiated austenitic stainless steels to the initiation of irradiation-assisted stress corrosion cracking (IASCC) was assessed. Solution annealed (SA), high purity (HP) type 304 stainless steel with and without additions of Mo and Si, and HP type 316L +Hf were strained by constant extension rate testing (CERT) in simu...
IntroductionExperimentalResultsDiscussionConclusions
Acknowledgments
Citations
... 发生。如 Ashida 等[71] 研究了中子辐照 316 不锈钢在 DO 与 DH 高温高压水环境中的 IASCC 扩展速率， 发 现 316 不锈钢在 6.3×10 -8 mol/L DO 环境中的腐蚀电 ...
... Irradiation-assisted stress corrosion cracking (IASCC) describes an enhancement of inherent susceptibility to stress corrosion cracking (SCC) for alloy which is simultaneously subjected to irradiation, mechanical stress, and an aggressive environment [1][2][3][4]. This degradation mode has been recognized as a major cause of failure for the core components in nuclear power plants, especially the baffle/former bolts in light water reactors [3,5]. ...
