Radiation-induced degradation of stainless steel light water reactor internals
Article Properties
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LanguageEnglish
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DOI (url)
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Publication Date2012/07/01
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Indian UGC (journal)
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Refrences105
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Citations79
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Edward A. Kenik
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Jeremy T. Busby
Cite
Kenik, Edward A., and Jeremy T. Busby. “Radiation-Induced Degradation of Stainless Steel Light Water Reactor Internals”. Materials Science and Engineering: R: Reports, vol. 73, no. 7-8, 2012, pp. 67-83, https://doi.org/10.1016/j.mser.2012.05.002.
Kenik, E. A., & Busby, J. T. (2012). Radiation-induced degradation of stainless steel light water reactor internals. Materials Science and Engineering: R: Reports, 73(7-8), 67-83. https://doi.org/10.1016/j.mser.2012.05.002
Kenik, Edward A., and Jeremy T. Busby. “Radiation-Induced Degradation of Stainless Steel Light Water Reactor Internals”. Materials Science and Engineering: R: Reports 73, no. 7-8 (2012): 67-83. https://doi.org/10.1016/j.mser.2012.05.002.
1.
Kenik EA, Busby JT. Radiation-induced degradation of stainless steel light water reactor internals. Materials Science and Engineering: R: Reports. 2012;73(7-8):67-83.
Journal Categories
Science
Chemistry
Science
Physics
Technology
Chemical technology
Technology
Electrical engineering
Electronics
Nuclear engineering
Materials of engineering and construction
Mechanics of materials
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Refrences
| Title | Journal | Journal Categories | Citations | Publication Date |
|---|---|---|---|---|
| Strain-induced precipitate dissolution in an irradiated austenitic alloy | Scripta Materialia |
| 10 | 2011 |
| 10.1016/S1369-7021(09)70294-9 | Materials Today |
| 2009 | |
| A review of irradiation effects on LWR core internal materials – IASCC susceptibility and crack growth rates of austenitic stainless steels | Journal of Nuclear Materials |
| 75 | 2011 |
| Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels | Acta Materialia |
| 151 | 2011 |
| Analysis of tensile deformation and failure in austenitic stainless steels: Part II – Irradiation dose dependence | Journal of Nuclear Materials |
| 15 | 2010 |
Citations
| Title | Journal | Journal Categories | Citations | Publication Date |
|---|---|---|---|---|
| Extending damage accumulation of commercial reactor irradiated 316 stainless steel with ion irradiation | Journal of Nuclear Materials |
| 2024 | |
| Interactions between irradiation-induced defects and dislocations in concentrated solid solution alloys | Journal of Nuclear Materials |
| 2024 | |
Effects of Ion Irradiation on Stage II Fatigue Crack Growth and Plasticity | Fatigue & Fracture of Engineering Materials & Structures |
| 2024 | |
A Link between Neutron and Ion Irradiation Hardening for Stainless Austenitic and Ferritic-Martensitic Steels | Metals |
| 1 | 2024 |
The Influence of Phase Formation on Irradiation Tolerance in a Nanocrystalline TiZrNbHfTa Refractory High‐Entropy Alloy | Advanced Engineering Materials |
| 1 | 2023 |
Citations Analysis
The category
Science: Chemistry 61
is the most commonly referenced area in studies that cite this article. The first research to cite this article was titled Materials challenges in nuclear energy and was published in 2013. The most recent citation comes from a 2024 study titled Interactions between irradiation-induced defects and dislocations in concentrated solid solution alloys. This article reached its peak citation in 2023, with 11 citations. It has been cited in 31 different journals, 12% of which are open access. Among related journals, the Journal of Nuclear Materials cited this research the most, with 26 citations. The chart below illustrates the annual citation trends for this article.