Analysis of Reactor Component Fluence Limits Using Damage Function Methods
Author:
Affiliation:
1. University of California at Santa Barbara Department of Chemical and Nuclear Engineering, Santa Barbara, California 93106
2. Hanford Engineering Development Laboratory, Irradiation Analysis Section P.O. Box 1970, Richland, Washington 99352
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT77-A31718
Reference24 articles.
1. Damage function data correlation for the yield stress of iron
2. Damage Functions and Data Correlation
3. Neutron energy-dependent damage function for analysis of austenitic steel creep data
4. The definition of damage functions from irradiation test data
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1. An evolution of understanding of reactor pressure vessel steel embrittlement;Journal of Nuclear Materials;2010-12
2. Correlation of irradiation creep data obtained in fast and thermal neutron spectra with displacement cross-sections;Journal of Nuclear Materials;1980-04
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