EDP Sciences logo
Web of Conferences logo
Rechercher
Menu
Accueil Tous les numéros Volume 225 (2020) EPJ Web Conf., 225 (2020) 03007 Références
Open Access
Numéro
EPJ Web Conf.
Volume 225, 2020
ANIMMA 2019 – Advancements in Nuclear Instrumentation Measurement Methods and their Applications
Numéro d'article 03007
Nombre de pages 8
Section Nuclear Power Reactors Monitoring and Control
DOI https://doi.org/10.1051/epjconf/202022503007
Publié en ligne 20 janvier 2020
  1. J.T. Goorley, et al., Initial MCNP6 Release Overview - MCNP6 version 1.0, LA-UR-13-22934, 2013. [Google Scholar]
  2. T. Kaiba, et al., Validation of neutron flux redistribution factors in JSI TRIGA reactor due to control rod movements, Appl. Radiat. Isot., vol. 104, pp. 34–42, 2015. doi:10.1016/j.apradiso.2015.06.026. [CrossRef] [PubMed] [Google Scholar]
  3. T. Goriˇcanec, et al., Evaluation of neutron flux and fission rate distributions inside the JSI TRIGA Mark II reactor using multiple in-core fission chambers, Annals of Nuclear Energy, vol. 111, pp. 407–440, 2018. [Google Scholar]
  4. J. Jensen-Tornehed, et al., The Nuclear Design and Core Management of the KRSKO Nuclear Power Plant Cycle 26, revision 1, Westinghouse Electric Company LLC, 2012. [Google Scholar]
  5. A. Trkov, M. Ravnik, H. Wimmer, B. Glumac, H. Bck, Application of the rod insertion method for control rod worth measurements in research reactors, Kerntechnik, vol. 60, pp. 255261, 1995. [Google Scholar]
  6. V. Merljak, M. Kromar, A. Trkov, Rod insertion method analysis - A methodology update ad comparison to boron dilution method, Annals of Nuclear Energy, vol. 113, pp. 96–104, 2018. [Google Scholar]
  7. M. Kromar, et. al, The Nuclear Design and Core Management of the Krˇsko NPP Cycle 26,, Institute Joˇzef Stefan, Ljubljana, Slovenia, IJSDP-11027, 2012. [Google Scholar]
  8. W. A. Rhoades, DOT IV, Version 4.2: Two Dimensional Discrete Ordinates Radiation Transport Code System, RSIC Code Package CCC-320, ORNL, Oak Ridge, Tenn., 1979. [Google Scholar]
  9. M. Kromar, A. Trkov, Nuclear Design Calculations of the NPP Krˇsko Core, Journal of Energy Technology, Vol. 2, pp. 41–50, November 2009. [Google Scholar]
  10. S. W. Mosher, et. al, ADVANTG An Automated Variance Reduction Parameter Generator, August 2015. [Google Scholar]
  11. J. R. Askew, F. J. Fayers, P. B. Kemshell, A General Description of the Code WIMS, J. Br. Nucl. Energy Soc., Vol. 5, p. 564, 1966. [Google Scholar]
  12. A. Trkov, GNOMER - Multigroup 3-Dimensional Neutron Diffusion Nodal Code, Institute Joˇzef Stefan, Ljubljana, Slovenia, IJS-DP-6688, March 1993. [Google Scholar]
  13. A. Trkov, M. Najˇzer, L. ˇSkerget, Variant of Green’s function Nodal method for Neutron Diffusion, J. Nucl. Sci. Technol., Vol. 27, pp. 766x2013;777, 1990. [Google Scholar]
  14. M. Kromar, S. Slaviˇc, A. Trkov, CTEMP: A Code for Thermohydraulic Calculations,, Institute Joˇzef Stefan, Ljubljana, Slovenia, IJS-DP-6143, February 1991. [Google Scholar]
  15. Ž Štancar, M. Kromar, B. Kos and L. Snoj, Construction of a Monte Carlo Benchmark Pressurized Water Reactor Core Model, In: Proceedings of 25th International Conference Nuclear Energy for New Europe, Slovenia, September 2016. [Google Scholar]
  16. j. L. Conlin, W. Ji, J. C. Lee, M. R. Martin, Pseudo Material Construct for Coupled Neutronic-Thermal-Hydraulic Analysis of VHTGR, Transactions of ANS, Vol. 91, 2005. [Google Scholar]
  17. F. B. Brown, The makxsf Code with Doppler Broadening, LA-UR-06-7002, 2006. [Google Scholar]
  18. P. Sauvan, et al., Development of the R2SUNED Code System for Shutdown Dose Rate Calculations, IEEE Transactions on Nuclear Science, vol. 63, pp. 375–384, 2016. [Google Scholar]
  19. L. Snoj, B. Kos, Ž Štancar, and M. Kromar, >Neutron Streaming Analysis and Shielding Determination, IJS work report, IJS-DP-12106, Ljublja [Google Scholar]