Abstracts and Available Papers Presented at the
2004 International RERTR Meeting

The 26^th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) was held in Vienna, Austria on November 7-12, 2004. The available abstracts and papers that were presented at this meeting are provided below.

NATIONAL PROGRAMS

• Opening Address
  Yuri Sokolov (IAEA, Austria)
• Opening Address
  Steve Black (DOE, NNSA, USA)
• Status and Progress of the RERTR Program in the Year 2004
  A. Travelli (ANL, USA)
• IAEA Activities related to Research Reactor Fuel Conversion and Spent Fuel Return Programs
  Ira N. Goldman, Pablo Adelfang and Iain G. Ritchie (IAEA, Austria)
• 2004 Status of RERTR Activities of CNEA - Argentina
  Audero M, Balart S, Boero N, Cabot P, Manzini A, Pasqualini E, Ruggirello G, Taboada, H (CNEA, Argentina)
• Progress with the Australian replacement research reactor
  M. I. Ripley, A. Irwin (ANSTO, Australia)
• Research Reactors in Austria - Present Situation
  H. Böck, A. Musilek, M. Villa (Atominstitut, Austria)

FUEL DEVELOPMENT & FABRICATION

• Post-Irradiation Analysis of Low Enriched U-Mo/Al Dispersion Fuel Miniplate Tests, RERTR 4 and 5
  G.L. Hofman, M.R. Finlay, Y.S. Kim (ANL, USA)
• RECH-1 Test Fuel Irradiation Status Report
  J. Marin, J. Lisboa, L. Olivares, J. Chavez (CCHEN, Chile)
• Development, Irradiation Testing and PIE of UMo Fuel at AECL
  D. F. Sears (AECL, Canada)
• MTR Fuel Plate Qualification in OSIRIS Reactor
  P. Sacristan, P. Boulcourt, S. Naury, L. Marchand, H. Carcreff, J. Noirot, D. Gallo-Lepage, (CEA, France)
• The VALMONT Experimental Programme for the Neutronic Qualification of the Umo/Al Fuel for the Jules-Horwitz Reactor
  C. Döderlein, M. Antony, D. Blanchet, J. Di Salvo, JP. Hudelot, N. Huot, A. Santamarina, P. Sireta, G. Willermoz (CEA, France)
• Irradiation Performance of U3Si LEU Fuels in HANARO
  H.T. Chae, C.S. Lee, I.C. Lim, H. Kim, B.J .Jun, H.R. Kim, J.M. Park, C.K. Kim, C.B. Lee, B.G. Kim, D.S. Sohn (KAERI, Korea)
• The Global Threat Reduction Initiative and Conversion of Isotope Production to LEU Targets
  A. J. Kuperman (NCI, USA)
• PIE of the 2nd Irradiation Test (KOMO-2) for Atomized U-Mo Dispersion Rod Fuels at KAERI
  C.K. Kim, H.J. Ryu, D.B. Lee, S.J Oh, K.H Kim, J.M Park, Y.S. Choo, D.G. Park, H.T. Chae, C.S. Lee, D.S Sohn (KAERI, Korea)
• Course of Pin Fuel Test in WWR-M Reactor Core
  A.S. Zakharov, G.A. Kirsanov, K.A. Konoplev (PNPI, Russia)
• An Investigation on the Irradiation Behavior of Atomized U-Mo/Al Dispersion Rod Fuels
  J.M. Park, H.J. Ryu, Y.S. Lee, D.B. Lee, S.J. Oh, B.O. Yoo, Y.H. Jung, D.S. Sohn, and C.K. Kim (KAERI, Korea)
• Update on Fuel Fabrication Development and Testing at Argonne National Laboratory
  C.R. Clark, T.C. Wiencek, M.R. Finlay, R.L. Briggs, D.M. Wachs, S.L Hayes, G.L. Hofman and C.J. Mothershead (ANL, USA)
• Increasing the Performance of U-Mo Fuels
  Enrique E. Pasqualini and Marisol López (CAC, Argentina)
• Reaction Layer between U-7wt%Mo and Al Alloys in Chemical Diffusion Couplers
  M. Mirandou, M. Granovsky, M. Ortiz, S. Balart, S. Aricó and L. Gribaudo (CNEA, Argentina)
• A Microstructurally-Based Model for the Evolution of Irradiation-induced recrystallization in U-Mo monolithic and Al-dispersion fuels
  J. Rest (ANL, USA)
• Thermomechanical DART Code Improvements for LEU VHD Dispersion and Monolithic Fuel Element Analysis
  H. Taboada , R. Saliba, M. Moscarda (CNEA, Argentina), Rest, J (ANL, USA)

MO-99 

• Status of ANSTO Mo-99 Production Using LEU Targets
  M. Druce , T. Donlevy , P. Anderson, G. Yeoh, D. Wassink, T Renhart, Ed Bradley (ANSTO, Australia), C. Jarousse, M. Febvre , J. Falgoux , J. Le Pape (CERCA, France)
• ANL Progress on the Coopertion with CNEA for the Mo-99 Production: Base-Side Digestion Process
  A.V. Gelis, K. J. Quigley, S. B. Aase, A. J. Bakel, A. Leyva, M. C. Regalbuto, and G. F. Vandegrift (ANL,USA)
• Thermoxid Sorbents for the Separation and Purification of 99Mo
  A. J. Bakel, S. B. Aase, K. J. Quigley, and G. F. Vandegrift (ANL, USA)
• Development of the Fabrication Technology of Wide Uranium Foils for Mo-99 Irradiation Target by Cooling-roll Casting Method
  K. H. Kim, M. K. Son, S. J. Oh, D. B. Lee, B. C. Lee, C. K. Kim and D. S. Sohn (KAERI, Korea)
• Making of Fission 99Mo from LEU Silicide(s): a Radiochemist’s View
  Z.I. Kolar and H.Th. Wolterbeek (Delft University of Technology, The Netherlands)
• Mo-99 Production on a LEU Solution Reactor
  R.W. Brown and L.A. Thome (TCI Medical, USA), V.Y. Khvostionov, (RRC Kurchatov Institute, Russia)

REACTOR CONVERSION ANALYSIS

• Analyses for Inserting Fresh LEU Fuel Assemblies Instead of Fresh HEU Fuel Assemblies in the Dalat Nuclear Research Reactor in Vietnam
  N. A. Hanan, J.R. Deen, and J. E. Matos (ANL, USA)
• Progress in Joint Feasibility Study of Conversion from HEU to LEU FUEL AT IRT-200, SOFIA
  T. Apostolov and S. Belousov (INRNE, Bulgaria), J. R. Deen, N. A. Hanan, and J. E. Matos (ANL,USA)
• Feasibility Study of the WWR-K Reactor Conversion to Low-Enriched Fuel
  F. Arinkin, Sh. Gizatulin, Zh. Zhotabaev, K. Kadyrzhanov, S. Koltochnik, P. Chakrov, L. Chekushina (KNNC, Kazakhstan), T. Zhantikin, S. Talanov (KAEC, Kazakhstan)
• Feasibility Study for LEU Conversion of the WWR-K Reactor at the Institute of Nuclear Physics in Kazakhstan Using a 5-Tube Fuel Assembly
  N.A. Hanan, J.R. Liaw and J. E. Matos (ANL, USA)
• Prospects of WWR-SM Reactor LEU Conversion and Spent Fuel Shipment Activity Status
  A. Rakhmanov, B. Yuldashev, U. Salikhbaev (INPAS, Uzbekistan)
• Core Configuration of the Syrian Reduced Enrichment Fuel MNSR
  M. Albarhoum (AEC, Syria)
• What the Difference to Use LEU and HEU Fuel Elements Separately or Together in a Research Reactor
  Şadi Kaya, Gulsen Ustun (CNRTC, Turkey)
• LVR-15 Reactor Performance and Transformation to Low Enriched Fuel
  J. Kysela, J. Ernest, M. Marek (NRIR, Czech Republic)
• Flux Enhancement Options for an LEU-Fueled MIT Reactor
  Thomas H. Newton, Jr., Edward E. Pilat, and Mujid S. Kazimi (MIT, USA)
• Nuclear Facility of the National Academy of Sciences on the Basis of Highly Enriched Uranium
  S. Chigrinov, V. Bournos, I. Serafimovich, Yu. Fokov, C. Routkovskaia, N. Voropay , H. Kiyavitskaya (JIPNR-Sosny, Republic of Belarus)
• Accelerator-Driven Subcritical Assembly: Concept Development and Analyses
  Y. Gohar, J. Bailey, H. Belch, D. Naberezhnev, P. Strons, I. Bolshinsky (ANL, USA)
• Performance of PARR-1 with LEU Fuel
  S. Pervez, M. Latif, I.H. Bokhari and S.Bakhtyar (PINSTECH, Pakistan)
• Monolithic Fuel and High-Flux Reactor Conversion
  A. Glaser (Darmstadt University, Germany)
• Reduced Enrichment Program for FRM-II, Status 2004
  A. Röhrmoser, W. Petry, K. Böning, N.Wieschalla (TUM, Germany)

SAFETY, SPENT FUEL, AND REGULATORY ISSUES

• Research Reactor Utilization: A Justification for Existence?
  Piani CSB (NECSA, Republic of South Africa)
• Use of Computational Fluid Dynamics (CFD) Tools for Fuel Assembly Analysis
  P. L. Garner and T. Sofu (ANL, USA)
• Safety Analysis of the WWR-M Reactor in Ukraine to Allow Operation Using LEU Fuel
  Y. P. Mahlers and A. G. Dyakov (KINR, Ukraine)
• The Renewed Spirit of Y-12
  D. Wall (NNSA, USA), M. Hassler, E. Parker (BWXT Y-12, USA)
• Y-12 Product Improvements Expected to Reduce Metal Production Costs and Decrease Fabrication Losses
  M. Hassler, E. Parker (BWXT Y-12, USA)
• The Need to Address the Larger Universe of HEU-Fuelled Reactors, Including Critical Assemblies, Pulsed Reactors, and Propulsion Reactors
  F. N. von Hippel (Princeton University, USA)
• Technical Economical and Legal aspects of Repatriation of Russian-Origin Research Reactor SNF to Russia
  Smirnov A., Kanashov B., Efarov S. (R&D Company “Sosny”, Dimitrovgrad, Russia) Lebedev A., (TENEX, Moscow, Russia) Kolupaev D., (“Mayak” plant, Ozersk, Russia)
• Successful Completion of a Time Sensitive MTR and TRIGA Indonesian Shipment
  C. Anne, J. Patterson (NAC International, USA), C. Messick (DOE, USA)
• Logistics of the Research Rector Fuel Cycle: AREVA Solutions
  D. Ohayon, L. Halle, P. Naigeon, P. Auziere (COGEMA, France), J. Falgoux, F. Obadia (CERCA, France)
• A Mobile Melt-Dilute Module for the Treatment of Aluminum Research Reactor Spent Fuel
  H. Peacock, D. Fisher, T. Adams, R. Sindelar, N. Iyer (SRNL, USA), D. Sell, K. Allen, E. Howden, B. Westphal (ANL, USA)
• Managememnt of Spent Fuel from Reserch Reactors - Brazilian Progress Report (Within the Framework of the IAEA Regional Project RLA-4/018)
  A. J. Soares,  J. E. R. Silva, (IPEN - CNEN/SP, Brazil)
• Extending the Foreign Spent Fuel Acceptance Program: Policy and Implementation Issues
  E. S. Lyman, (UCS, USA)

POSTER SESSION

• Twenty-five Years Supporting RERTR Activities from CNEA MTR Fuel Fabrication Plant (ECRI)
  L. Alvarez, N. Boero, J. Fabro, M. Restelli, D. Podestá, G. Rossi (CNEA, Argentina)
• Monte Carlo Neutron Transport Simulation of the Ghana Research Reactor-1
  S. Anim-Sampong*, B.T. Maakuu, E.H.K. Akaho (GAEC, Ghana)
• An Indian Perspective for Transportation and Storage of Spepnt Fuel
  P.K. Dey  (BARC, India)
• Prediction of Flow Instability during Natural Convection
  K. Farhadi (AEOI, Iran)
• High Flux Reactor Evolutions and Improvements
  H. GUYON (ILL, France)
• Fuel Burnup Measurement of Spent Fuel Using Gamma Spectroscopy Technique
  C. Pereda, C. Henríquez, J. Klein and J. Medel (CCEN, Chile)
• Conceptual Analysis of the Fuel Management Strategy for the RA-3 Research Reactor at 10 MW
  A. M. Lerner, M. Madariaga, R. Waldman (NRA, Argentina)
• Photon Source and Shielding Studies Related to the Spent Fuel Storage of the RA Reactor
  M. Milošević (VINS, Serbia)
• CNEA Experiments to Apply Friction Stir Welding to Encase U-Mo Foils in Al
  P. Cabot, A. Moglioni, M. Mirandou, S. Balart (CNEA, Argentina)
• A Neutronic Feasibility Study for HEU-LEU Conversion of the Reactor PIK
  Y. V. Petrov, A. N. Erykalov, M. S. Onegin (PNPI, Russia)
• Set Up of U-Mo Power Production by HMD Process
  Enrique E. Pasqualini, Marisol López and Alfredo Gonzalez (CAC, Argentina)
• Corrosion of Spent Nuclear Fuel Aluminum Cladding in Ordinary Water
  M. Pešić, T. Maksin, G. Jordanov, R. Dobrijević (VINS, Serbia)
• The Metal and Concrete Cask for SNF and its Radiation Protection Quality Control
  N.D. Shchigolev, O.M. Golubev (PNPI, Russia)
• Specificity in the Licensing Process of Reduced Enrichment in the Bulgarian Research Reactor
  M. Vitkova, I. Gorinov (NRA, Bulgaria)
• Analysis of Typical Transients in the Generic 10 MW IAEA MTR Research Reactor by RELAP5/3.2
  A. Bousbia-salah (UP, Italy), T. Hamidouche (CRNA, Algeria), F. D’Auria (UP, Italy)