Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments Part II: Stress Corrosion Cracking-Reference-Cited by-同舟云学术

Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments Part II: Stress Corrosion Cracking

Published:2017-10-07 Issue: Volume: Page:2177-2188
ISSN:2367-1181
Container-title:The Minerals, Metals & Materials Series
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Author:

Wang Mi,Song Miao,Was Gary S.,Nelson L.,Pathania R.

Publisher

Springer International Publishing

Link

http://link.springer.com/content/pdf/10.1007/978-3-030-04639-2_146

Reference22 articles.

1. S. Bruemmer, New issues concerning radiation-induced material changes and irradiation-assisted stress corrosion cracking in light water reactors, in Proceeding of 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors. (Houston, TX, 2002)

2. O. Chopra, A. Rao, A review of irradiation effects on LWR core internal materials—Neutron embrittlement. J. Nucl. Mater. 412, 195–208 (2011)

3. O. Chopra, A. Rao, A review of irradiation effects on LWR core internal materials—IASCC susceptibility and crack growth rates of austenitic stainless steels. J. Nucl. Mater. 409, 235–256 (2011)

4. P. Andresen, F. Garner, J. Gorman, S. Maloy, J. Nelson, L. Tan, T. Toloczko, G. Was, Technical report: critical issues report and roadmap for the advanced radiation-resistant materials program, EPRI, Palo Alto, CA: 2012. 1026482, (2012)

5. F. Garner, B. Oliver, L. Greenwood, D. Edwards, S. Bruemmer, M. Grossbeck (2002) Generation and retention of helium and hydrogen in austenitic steels irradiated in a variety of LWR and test reactor spectral environments. Pacific Northwest National Laboratory (PNNL), Richland, WA (US)