Open Access
| Issue |
EPJ Web Conf.
Volume 153, 2017
ICRS-13 & RPSD-2016, 13th International Conference on Radiation Shielding & 19th Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society - 2016
|
|
|---|---|---|
| Article Number | 07019 | |
| Number of page(s) | 6 | |
| Section | 7. Poster Presentations | |
| DOI | https://doi.org/10.1051/epjconf/201715307019 | |
| Published online | 25 September 2017 | |
- VS. Neustroev, F.A. Garner Journal of Nuclear Materials 386-388 (2009) 157-160. [CrossRef] [Google Scholar]
- B.Z. Margolin, I.P. Kursevich, A.A. Sorokin, V.S. Neustrojev: “The Relationship of Radiation Embrittlement and Swelling for Austenitic Steels for WWER Internals”, Proceedings of the ASME 2009, Pressure Vessels and Piping conference, Prague, 2009. [Google Scholar]
- J. L. Nelson et al., Proceedings of the 16thInternational Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Asheville, USA, 2013. [Google Scholar]
- A.S. Kalchenko, V.V. Bryk, N.P. Lazarev, V.N. Voyevodin, F.A. Garner, Prediction of void swelling in the baffle ring of WWER-1000 reactors for service life of 30-60 years, Journal of Nuclear Materials, Volume 437, Issues 1-3, June 2013, Pages 415-423, ISSN 0022-3115. [CrossRef] [Google Scholar]
- Norgett, M. J., Robinson, M. T. and Torrens, I. M. A proposed method of calculating v displacement dose rates. Nucl. Eng. Des. 33,50–54 (1975). [Google Scholar]
- R. S. Averback and T. Diaz de la Rubia, Displacement damage in irradiated metals and semiconductors, in Solid State Physics, edited by H. Ehrenfest and F. Spaepen, volume 51, pages 281-402, Academic Press, New York, 1998. [Google Scholar]
- D. Harutyunyan, S. Vandlik, M. Schulc, M. Ruscak, E. Novak, Applicability of LR-0 mock-up results to VVER-1000 reactor pressure vessel issues, Annals of Nuclear Energy, Volume 98, December 2016, Pages 157-165, ISSN 0306-4549. [CrossRef] [Google Scholar]
- M. Košt’ál, V. Rypar, M. Švadlenková, The pin power distribution in the VVER-1000 mock-up on the LR-0 research reactor, Nucl. Eng. Des., 242 (2012), pp. 201-214 ISSN 0029-5493 [CrossRef] [Google Scholar]
- M. Košt’ál, M. Švadlenková, J. Milčák, Absolute determination of power density in the VVER-1000 mock-up on the LR-0 research reactor, Appl. Radiat. Isot., 78 (2013), pp. 38-45 ISSN 0969-8043 [CrossRef] [PubMed] [Google Scholar]
- M. Košt’ál, F. Cvachovec, V. Rypar, V. Juříček, Calculation and measurement of neutron flux in the VVER-1000 mock-up on the LR-0 research reactor, Annals of Nuclear Energy, Volume 40, Issue 1, February 2012, Pages 25-34, ISSN 0306-4549 [CrossRef] [Google Scholar]
- Greenwood, L. R. and Smither, R. K. SPECTER; neutron damage calculations for materials irradiations. ANL/FPP/TM-197. Argonne National Laboratory (1985). [Google Scholar]
- IAEA/NDS IRDF-2002 Damage Cross Section File 2002, http://wwwndsorg/irdf2002/data/irdf2002_damage.dat [Google Scholar]
- M.B. Chadwick, et al. S.1.: ENDF/B-VII.1 Nuclear data for science and technology: cross sections, covariances, fission product yields and decay data Nucl. Data Sheets, 112 (2011), pp. 2887-2996 [CrossRef] [Google Scholar]
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