Displacement damage cross section and mechanical properties calculation of an Es-Salam research reactor aluminum vessel-Reference-Cited by-同舟云学术

Displacement damage cross section and mechanical properties calculation of an Es-Salam research reactor aluminum vessel

Published:2017-10-26 Issue:11 Volume:28 Page:
ISSN:1001-8042
Container-title:Nuclear Science and Techniques
language:en
Short-container-title:NUCL SCI TECH

Author:

Saad Djillali,Benkharfia Hocine,Izerrouken Mahmoud,Benyahia Ahmed Ali,Ait-Abderrahim Hamid

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

http://link.springer.com/article/10.1007/s41365-017-0319-3/fulltext.html

Reference30 articles.

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2. M. Kolluri, Radiation Effects in Materials, in Neutron Irradiation Effects in 5xxx and 6xxx Series Aluminum Alloys: A Literature Review, ed. by A. Waldemar (Intech, Monteiro, 2016), pp. 393–411

3. H. Ju Jin, T. Kyu Kim, Neutron irradiation performance of Zircaloy-4 under research reactor operating conditions. Ann. Nucl. Energy 75, 309–315 (2015). doi: 10.1016/j.anucene.2014.08.042

4. M. R. James, D. B. Pelowitz et al., Technical Report: MCNP6 User’s Manual Code Version 6.1.1beta (LA-CP-14-00745, 2011), (Los Alamos National Laboratory, 2014)

5. SRIM-2013 software package (2013), http://www.srim.org/SRIM/SRIMLEGL.htm . Accessed Sept 2014

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