Open Access
Numéro
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
Numéro d'article 07041
Nombre de pages 5
Section 7. Poster Presentations
DOI https://doi.org/10.1051/epjconf/201715307041
Publié en ligne 25 septembre 2017
  1. DOORS 3.2a, Program Package for One, Two and Three Dimensional Discrete Ordinates Transport (CCC-650, RSICC, ORNL, 2003) [Google Scholar]
  2. K. Ilieva, S. Antonov, S. Belousov, Nucl. Sci. & Eng. 122 No. 1, 131-135 (1996) [CrossRef] [Google Scholar]
  3. K. Ilieva, T. Apostolov, I. Penev, S. Belousov, E. Taskaev, S. Antonov, T. Petrova, P. Tzokov, Z. Bojadjiev, Nucl. Engn. & Design 160, 257–260 (1996) [CrossRef] [Google Scholar]
  4. A. Thornton, TA. Lewis, J.R. Mossop, C.J. Page, S.A. Haddock, 10th International Symposium on Reactor Dosimetry (Osaka, 1999) [Google Scholar]
  5. J. Hep, A. Konečná, V. Kr“fsl, V. SmutnST, Reactor Dosimetry 14thInternational Symposium (Bretton Woods, 2011) [Google Scholar]
  6. V. Krýsl, P. Mikoláš, J. Šůstek, K. Vlachovský, Description of program MOB Y-DICK with changes for VVER-I000 (ŠKODA JS, 2015) [Google Scholar]
  7. BUGLE-B7/VITAMIN-B7, Broad-Group and Fine-Group and Coupled Neutron/Gama Cross-Section Libraries Derived from ENDF/B-VILO Nuclear Data (DLC-245, RSICC, ORNL, 2011) [Google Scholar]
  8. BUGLE-96, Coupled 47 Neutron, 20 Gamma-Ray Group Cross Section Library Derived from ENDF/B-VI for LWR Shielding and Pressure Vessel Dosimetry Applications (DLC-185, RSICC, ORNL, 1996) [Google Scholar]
  9. P. Borodkin, G. Borodkin, N. Khrennikov, Methodology of Fuel Burn Up Fitting in VVER-I 000 Reactor Core by Using New Ex-Vessel Neutron Dosimetry and In-Core Measurements and its Application for Routine Reactor Pressure Vessel Fluence Calculations, EPJ Web of Conferences, Volume 106 (2016), ISRD 15 — International Symposium on Reactor Dosimetry [Google Scholar]