Computational analysis of irradiation facilities at the JSI TRIGA reactor
Tóm tắt
Từ khóa
Tài liệu tham khảo
Aghara, 2006, Characterization and quantification of an in-core neutron irradiation facility at a TRIGA II research reactor, Nucl. Instrum. Methods B, 248, 181, 10.1016/j.nimb.2006.04.074
Chadwick, M.B., et al., 2006. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology, Nuclear Data Sheets, Special issue on Evaluated Nuclear Data File ENDF/B-VII.0. Available from National Nuclear Data Center, Brookhaven 〈http://www.nndc.bnl.gov/exfor2/endf00.htmS〉 (February 2009).
ICSBEP, 2009. International Handbook of Evaluated Critical Safety Benchmark Experiments Organization for Economic Cooperation and Development – Nuclear Energy Agency, NEA/NSC/DOC(95)03, Paris, published on DVD, ISBN: 978-92-64-99054-8.
Jaćimović, 2010, Validation of calculated self-shielding factors for Rh foils, Nucl. Instrum. Methods A, 622, 399, 10.1016/j.nima.2010.02.053
Jeraj, R., Ravnik, M., 1999. TRIGA Mark II Reactor: U(20) – Zirconium Hydride Fuel Rods in Water with Graphite Reflector, Jožef Stefan Institute.
Jonah, 2006, Standardization of NIRR-1 irradiation and counting facilities for instrumental neutron activation analysis, Appl. Radiat. Isot., 64, 818, 10.1016/j.apradiso.2006.01.012
Kramberger, 2007, Annealing studies of effective trapping times in silicon detectors, Nucl. Instrum. Methods A, 571, 608, 10.1016/j.nima.2006.10.399
Kramberger, 2007, Impact of annealing of trapping times on charge collection in irradiated silicon detectors, Nucl. Instrum. Methods A, 579, 762, 10.1016/j.nima.2007.05.294
Lin, 2006, Neutron flux parameters at irradiation positions in the new research reactor FRM-II, Nucl. Instrum. Methods A, 564, 641, 10.1016/j.nima.2006.04.024
Meftah, 2006, Neutron flux optimization in irradiation channels at NUR research reactor, Ann. Nucl. Energy, 33, 1164, 10.1016/j.anucene.2006.08.003
Merz, 2011, Neutron flux measurements at the TRIGA reactor in Vienna for the prediction of the activation of the biological shield, Appl. Radiat. Isot., 69, 1621, 10.1016/j.apradiso.2011.05.019
Nagels, 2009, Determination of the irradiation field at the research reactor TRIGA Mainz for BNCT, Appl. Radiat. Isot., 67, S242, 10.1016/j.apradiso.2009.03.080
Snoj, L., Ravnik, M., 2006. Calculation of power density with MCNP in TRIGA reactor. In: Proceedings of the International Conference Nuclear Energy for New Europe 2006, Portorož, Slovenia, Paper no. 102.
Snoj, 2008, Power peakings in mixed TRIGA cores, Nucl. Eng. Des., 238, 2473, 10.1016/j.nucengdes.2008.02.005
Snoj, 2010, Calculation of kinetic parameters for Mixed TRIGA cores with Monte Carlo, Ann. Nucl. Energy, 37, 223, 10.1016/j.anucene.2009.10.020
Snoj, 2011, Advanced methods in teaching reactor physics, Nucl. Eng. Des., 241, 1008, 10.1016/j.nucengdes.2010.02.040
Snoj, 2011, Analysis of neutron flux distribution for the validation of computational methods for the optimization of research reactor utilization, Appl. Radiat. Isot., 69, 136, 10.1016/j.apradiso.2010.08.019
Stamatelatos, 2007, Monte Carlo simulation of the Greek research reactor neutron irradiation facilities, Nucl. Instrum. Methods B, 263, 136, 10.1016/j.nimb.2007.04.074
Trkov, 1992, Reactivity measurements in a close-to-critical TRIGA reactor using a digital reactivity meter, Kerntechnik, 57, 296, 10.1515/kern-1992-570511
Trkov, 2009, On the self-shielding factors in neutron activation analysis, Nucl. Instrum. Methods A, 610, 553, 10.1016/j.nima.2009.08.079
X-5 Monte Carlo Team, 2004 MCNPTM – A General Monte Carlo N-Particle Transport Code, Version 5, LA-UR-03-1987.
Žerovnik, G., 2007. Karakterizacija nevtronskega polja v obsevalnih kanalih reaktorja TRIGA. Diploma Work, Faculty of Mathematics and Physics, University of Ljubljana, Slovenia (in Slovene).