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Accueil Tous les numéros Volume 170 (2018) EPJ Web Conf., 170 (2018) 04012 Références
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Numéro
EPJ Web Conf.
Volume 170, 2018
ANIMMA 2017 – Advancements in Nuclear Instrumentation Measurement Methods and their Applications
Numéro d'article 04012
Nombre de pages 5
Section Research reactors
DOI https://doi.org/10.1051/epjconf/201817004012
Publié en ligne 10 janvier 2018
  1. Snoj, L., Smodiš, B., 2011. 45 Years of TRIGA Mark II in Slovenia. In: Proceedings of the International Conference Nuclear Energy for New Europe 2011, Bovec, Slovenia, Paper no. 401. [Google Scholar]
  2. Barbot, L., Domergue, C, Breaud, S., Destouches, C., Villard, J.-F., Snoj, L., Štancar, Ž., Radulović, V., Trkov, A. 2013. Neutron held characterization of irradiation locations applied to the Slovenian TRIGA reactor. In: Proceedings of the International Conference Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2013. Marseille, France, doi: 10.1109/AN-IM MA. 2013.6727954. [Google Scholar]
  3. Filliatre, P., Oriol, L., Jammes, C., Vermeeren, L., 2008. Reasons why Plutonium 242 is the best fission chamber deposit to monitor the fast component of a high neutron flux. Nuclear Instruments And Methods in Physics Research - Section A, 593 (3), pp. 510–518. [CrossRef] [Google Scholar]
  4. Filliatre, L., Oriol, L., Jammes, C., Vermeeren, L., 2009. Joint estimation of the fast and thermal components of a high neutron flux with a two one-line detector system. Nuclear Instruments and Methods in Physics Research - Section A. 603 (3), pp. 415–420. [CrossRef] [Google Scholar]
  5. Goorley, T., et al., 2012. Initial MCNP 6 Release Overview. LA-UR-11-07082. Los Alamos National Laboratoiy, also Nuclear Technology, 180, pp. 298–315 (Dec 2012). [Google Scholar]
  6. Chadwick, M. B. et al., 2011. ENDF/B-VII.l Nuclear Data for Science and Technology: Cross Sections. Covariances. Fission Product Yields and Decay Data. LA-UR 11-05121. Los Alamos National Laboratoiy, also Nuclear Data Sheets, 112 Issue 12. pg. 2887–2996 (Dec 2011). [Google Scholar]
  7. Jeraj, R., Ravnik, M., 1999. TRIGA Mark II Reactor: U(20)-Zirconium Hydride Fuel Rods in Water with Graphite Reflector, IEU-COMP-THERM-003, International Handbook of Evaluated Critical Safety Benchmark Experiments, Organization for Economic Cooperation and Development - Nuclear Energy Agency, NEVNSC/SOQ95)03, Paris, 1999. [Google Scholar]
  8. ICSBEP, 2009. International Handbook of Evaluated Critical Safety Benchmark Experiments, Organization for Economic Cooperation and Development - Nuclear Energy Agency. NE.VNSC/DOC(95)03. Paris, published on DVD. ISBN 978-92-64-99054-8. [Google Scholar]
  9. Ravnik, M., Jeraj, R., 2003. Research reactor benchmarks. Nucl. Sci. Eng. 145, 145–152. [CrossRef] [Google Scholar]
  10. Snoj, L., Ravnik, M., 2008. Power peakings in mixed TRIGA cores. Nucl. Eng. Des. 238 (9), 2473–2479. [CrossRef] [Google Scholar]
  11. Snoj, L., Kačtič, A. Žerovnik, G., Ravnik, M., 2010. Calculation of Kinetic Parameters for Mixed TRIGA Cores with Monte Carlo. An. Nucl. Ene. 37 (2), 223–229, doi: 10.1016/j. anucene.2009.10.020. [Google Scholar]
  12. Snoj, L., Trkov, A., Jaćimović, R, Rogan, P Žerovnik, G., Ravnik, M., 2011. Analysis of neutron flux distribution for the validation of computational methods for the optimization of research leactor utilization. Appl. Radiat. Isot. 69, 136–141, doi: 10.1016/j.apradiso.2010.08.019. [Google Scholar]
  13. Žerovnik, G., Kaiba, T., Radulović, V., Jazbec, A., Rupnik, S., Barbot, L., Fourmentel, D., Snoj, L, 2015. Validation of the neutron and gamma fields in the JSI TRIGA leactor using in-core fission and ionization chambers. Appl. Radial. Isot. 96, 27–35, doi: 10.1016/j. aprad i so. 2014.10.026. [Google Scholar]
  14. Štancar, Ž., Snoj, L., Barbot, L. Domergue, C., 2015. Evaluation of Fission Rate Profile Experimental Benchmark at the JSI TRIGA Mark II Reactor Using Monte Carlo Method. In: Proceedings of the Joint International Conference on mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method. 19-23 April 2015, Tennessee, USA. [Google Scholar]
  15. Žerovnik, G., Podvratnik, M., Snoj, L., 2014. On normalization of fluxes and reaction rates in MCNP criticality calculations. An. Nucl. Ene. 63, 126–128, doi: 10.1016/J.anucene.2013.07.045 [Google Scholar]
  16. Kaiba, T., et al., 2017. Evaluation of neutron flux and fission rate distributions inside the JSI TRIGA Mark II reactor using multiple in-core fission chambers, submitted to Annals of Nuclear Energy. [Google Scholar]