Author:
Troyanov V. M.,Grachev A. F.,Zabud’ko L. M.,Skupov M. V.
Publisher
Springer Science and Business Media LLC
Subject
Nuclear Energy and Engineering
Reference10 articles.
1. F. Delage, J. Carmack, C. Lee, et al., “Status of advanced fuel candidates for sodium fast reactor within the Generation IV International Forum,” J. Nucl. Mater., 441, 515–519 (2013).
2. D. Crawford, D. Porter, and S. Hayes, “Fuels for sodium-cooled fast reactors: US perspective,” ibid., 371, 202–231 (2007).
3. B. D. Rogozkin, N. M. Stepennova, Yu. E. Federov, et al., “Results of tests of mixed mononitride fuel (45%PuN+55%UN and 60%PuN+40%UN) in the BOR-60 reactor to burnup ~12% h.a.,” At. Énerg., 110, No. 6, 332–346 (2011).
4. A. Sengupta, “Experience on mixed carbide fuels with high Pu content for Indian fast breeder reactor – an overview,” J. Nucl. Mater., 385, No. 1, 161–164 (2009).
5. F. N. Kryukov, O. N. Nikitin, S. V. Kuz’min, et al., “State of nitride fuel after irradiation in fast reactors,” At. Énerg., 112, No. 6, 336–341 (2012).
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