Microstructural Analysis of MTFR Fuel Plates Damaged by a Coolant Flow Blockage
A. Leenaers, S. Van Den Berghe (SCK-CEN) - Belgium
Status of the VIND Program, November 2008
M. Pesic (Vinca Institute of Nuclear Sciences) - Republic of Serbia
Upgraded Reactor Systems for Enhanced Safety at TRIGA-INR
M. Preda, M. Ciocanescu, E. Mugurel Ana (Institute for Nuclear Research) – Romania
Uranium Contamination in Primary Circuit of the LVR-15 Reactor
L. Viererbl, Z. Lahodova, V. Klupak, F.Sus. M. Marek (Nuclear Research Institute Rez plc) - Czech Republic
Analyses of IRT, Sofia LEU Core: Steady-State Thermal-Hydraulic and Accident Analyses
T. Apostolov, S. Belousov (Institute for Nuclear Research and Nuclear Energy of Bulgarian) – Bulgaria, N. Henan, J. Matos (RERTR Program, Argonne National Laboratory) – US
Corrosion Behavior of Aluminum Alloy Coupons Submerged in the Storage Pools of Spent Nuclear Fuel in Chile
C. Lamas, J. Klein, H. Torres, D. Calderón (Commisión Chilean de Energía Nuclear) – Chile
14 MW INR-TRIGA Research Reactor Core Conversion - Emergency Preparedness Challenges
S. Margeanu,C.A. Margeanu, C. Iorgulis, M. Ciocanescu (Institute for Nuclear Research) – Romania
Synthesis and Characterization of Gamma UMo Powders Fabricated via the HDH Technique
F.B. Vaz De Oliveira (Nuclear and Energy Research Institute, IPEN/CNEN), H. Gracher Riella (Federal University of Santa Catarina) – Brazil
Irradiation Results of Multi-wire U-Mo Monolithic Fuel for HANARO Research Reactor
Y-S Lee, H-J Ryu, J-M Park, J-M Oh, B. Yoo, C-K Kim (Korea Atomic Energy Research Institute) – Korea
Self-Assessment of Application of the Code of Conduct on the Safety of Research Reactors
Y.R. Mamani-Alegria, J.R. Salgado-Gonzalez (National Commission on Nuclear Safety and Safeguards) – Mexico
An Investigation on Homogeneous Blending for Large Particle U-Mo and Al Powders by Multi-Sieve Dropping Method
C.K. Kim, J.M. Oh, C.G. Ji, J.S. Park, (Korea Atomic Energy Research Institute), G.H. Choi (Chungnam National University), J.M. Park (Korea University) – Korea
The Management System Evolution of Research Nuclear Reactor IEA-R1
T.C. Salvetti, R.P. Paiva, R. Frajndlich, G.C. Longo (Brazilian Nuclear Energy Comission - CNEN / Nuclear Research Institute IPEN-CNEN/SP) – Brazil
Benchmark of Heat Deposition Measurement Techniques in the SAFARI-1 Reactor Using MCNP5
B.M. Makgopa, M. Belal (South African Nuclear Energy Corporation, NECSA) - South Africa
LEU Fuel Disposition at WWR-M Reactor after Irradiation Test
K.A. Konoplev, S.P. Orlov, A.S. Zakharov (Pertersburg Nuclear Physics Institute) – Russia
Physical Properties of Monolithic U8MO
R.M Hengstler, C. Bogenberger, H. Breitkreutz, R. Jungwirth, W. Petry, W. Schmid (FRM II TU Munich); G. Gradel, N. Wieschalla (AREVA NP GmbH); W.W. Schmahl, J. Schneider (LMU Munich); L. Beck, W. Carli (Maier-Leibnitz-Laboratorium) – Germany; C. Jarousse (AREVA – CERCA) - France
Current Utilization and Long Term Strategy of the Finnish TRIGA Research Reactor FiR 1
I. Auterinen, S. Salmenhaara (VTT Technical Research Centre) – Finland
Studying of influence of a neutron irradiation on element contents and structures of aluminum alloys SAV-1 and AMG-2
U. S. Salikhbaev, S. A. Baytelesov, F.R. Kungurov, A. S. Saidov (Institute of Nuclear Physics of Academy of Sciences) – Uzbekistan
The Spent Fuel Storage at the Dalat Nuclear Research Reactor
P. Van Lam, N. Nhi Dien, L. Ba Vien, L. Vinh Vinh, H. Ton Nghiem, N. Minh Tuan, N. Kien Cuong (Nuclear Research Institute) - Vietnam
TEM Characterization of Irradiated RERTR Dispersion Fuel
J. Gan,D. D. Keiser, Jr., D. M. Wachs (Idaho National Laboratory); B. D. Miller, T. R. Allen (University of Wisconsin) - USA
Stereometric Analysis of Gas Porosity of Fission products in Irradiated U-Мo Fuel
O.A. Golosov, S.А. Аverin, V.L. Panchenko, M.S. Lyutikova (Institute of Nuclear Materials) – Russia
Neutronic study regarding transmutation fuel research at Jules Horowitz Reactor
T. Stummer (Vienna University of Technology/Atominstitute) - Austria, Y. Peneliau, C. Gonnier (CEA Cadarache) – France
INSPECTION EXPERIENCE WITH IEA-R1 SPENT FUEL AND NON-DESTRUCTIVE METHODS FOR QUALIFICATION OF HIGH DENSITY LEU FUEL (U3Si2-Al) AT IPEN/CNEN-SP
J.E. Rosa da Silva, A. Teixeira e Silva, L.A. Albiac Terremoto (Instituto de Pesquisas Energéticas e Nucleares) - Brazil
Investigation of the Applications of Positron Annihilation Spectroscopy to RERTR Fuel Plates
M. A. Okuniewski, D. W. Akers, D. E. Burkes (Idaho National Laboratory) - US
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