Abstracts and Available Papers Presented at the
2003 International RERTR Meeting

The 25^th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) was held in Chicago, Illinois on October 5-10, 2003.  The available abstracts and papers that were presented at this meeting are provided below.

NATIONAL PROGRAMS

• Status and Progress of the RERTR Program in the Year 2003
  A. Travelli (ANL, USA)
• Overview of the Status of Research Reactors Worldwide
  P. Adelfang, I. Ritchie, and B. Dodd (IAEA, Austria)
• Russian Research Reactor Fuel Return Program Starts Shipping Fuel To Russia
  T. Dedik, I. Bolshinsky, (DOE, USA) and A. Krass (U.S. Department of State, USA)
• The United States Foreign Research Reactor Spent Nuclear Fuel Acceptance Program: Progress at the Midpoint
  C. Messick, A. Thrower, and J. Wade (DOE, USA)
• The Current Status and Future Plans of the Russian RERTR Program
  V. Bezzubtsev, N. Arkhangelsky (MINATOM, Russia), V. Aden (RDIPE, Russia), V. Chernyshov (JSC TVEL, Russia), A. Vatulin (VNIINM, Russia)
• Accelerating the Design and Testing of LEU Fuel Assemblies for Conversion of Russian-Designed Research Reactors Outside of Russia
  J.E. Matos (ANL, USA)
• Status as of October 2003 of the French UMo Group Development Program
  J.M. Hamy (Framatome-ANP, France), F. Huet, B. Guigon (CEA-Cadarache, France), P. Lemoine, (CEA-Saclay, France), C. Jarousse (CERCA-Framatome-ANP, France) M. Boyard, (Technicatome, France), J.L. Emin
• Status of RERTR Activities in Argentina
  L. Alvarez, N. Boero, E. Pasqualini, P. Echenique, G. Ruggirello (CNEA, Argentina)
• Status of Reduced Enrichment Program for Research Reactors in Japan
  Y. Nakagome (Kyoto University, Japan) and K. Shimizu (JAERI, Japan)
• RERTR-Related Program in Indonesia
  A. Suripto, Sigit, A. Mutalib, Adiwardoyo S. Supardjo (BATAN, Indonesia)

MO-99

• The LEU Target Development and Conversion Program for the Maple Reactors and New Processing Facility
  G. Malkoske (MDS Nordion, Canada)
• ANL Progress in Minimizing Effects of LEU Conversion on Calcination of Fission-Product ⁹⁹Mo Acid Waste Solution
  A. Bakel, G.F. Vandegrift, K.J. Quigley, S.B. Aase, M.K. Neylon, K.P. Carney, A. Travelli (ANL, USA)
• ANL Progress in Developing an LEU Target and Process for Mo-99 Production: Cooperation with CNEA
  A. Guelis, G.F. Vandegrift, S.B. Aase, A.J. Bakel, J. Falkenberg, M.C. Regalbuto, K. Quigley (ANL, USA)
• Physics Study for a LEU Mo Target Irradiation at HANARO
  B.C. Lee, C.S. Lee, H. Kim (KAERI, Korea)

FUEL DEVELOPMENT

• Full-Sized Plates Irradiation with High UMo Fuel Loading – Final Results of IRIS 1 Experiment
  F. Huet, V. Marelle, J. Noirot, P. Sacristan, P. Lemoine (CEA, France)
• Recent Observations at the Postirradiation Examination of Low-Enriched U-Mo Miniplates Irradiated to High Burnup
  G.L. Hofman, Y.S. Kim, M.R. Finlay (ANSTO, Australia), J.L. Snelgrove, S.L. Hayes, M.K. Meyer, C.R. Clark (ANL, USA)
• Reaction Layer Between U-7wt%Mo/Al In Diffusion Couples
  M. Mirandou, S. Balart, M. Ortiz, M. Granovsky (CNEA, Argentina)
• Prediction Model for Oxide Thickness on Aluminum Alloy Cladding During Irradiation
  Y.S. Kim, G.L. Hofman, N.A. Hanan and J.L. Snelgrove (ANL, USA)
• Major Results on the Development of High Density U-Mo Fuel and Pin-Type Fuel Elements Executed Under Russian RERTR Program and in Cooperation with ANL (USA)
  A. Vatulin, A. Morozov, Y. Stetsky, V. Suprun, I. Dobrikova, Y. Trifonov, V. Mishunin, V. Sorokin (VNIINM, Russia)
• Conditions and Preliminary Results of Low Enrichment U-Mo Pin Type Fuel Testing in the MIR Reactor
  A.L. Izhutov, N.G. Gataulin, V.V. Pimenov, M.N. Svyatkin, V.A. Starkov (RIAR, Russia)
• Tests of Pin-Type Fuel Elements in the WWR-M Reactor
  G.A. Kirsanov, K. Konoplev, R.G. Pikulik, D.V. Tchmshkyan, L.V. Tedoradze, A.S. Zakharov (PNPI, Russia)
• LEU Fuel Development Progress and Programs, BWX Technologies, Inc.
  B.W. Pace and G.R. Gale (BWXT, USA)
• CERCA’s Experience in UMo Fuel Manufacturing
  Ch. Jarousse, L. Lavastre, M. Grasse (CERCA, France)
• Manufacturing and Licensing of a Lead Test Assembly for the R2 Reactor
  J.P. Durand, F. Obadia, Ch. Jarousse, Y. Lavastre, M. Grasse (CERCA, France), J.L. Falgoux (Framatome, France), U. Lindelöw (Studsvik Nuclear, Sweden)
• Modeling RERTR Experimental Fuel Plates Using the Plate Code
  S.L. Hayes, M.K. Meyer, G.L. Hofman, J.L. Snelgrove (ANL, USA)
• DART-TM: A Thermomechanical Version of Dart Code for LEU VHD Dispersed and Monolithic Fuel Analysis
  R. Saliba, H. Taboada, M.V. Moscarda (CNEA, Argentina), J. Rest (ANL, USA)
• The Chilean LEU Fuel Fabrication Program:  Status Report
  J. Marin, M. Barrera, J. Lisboa, O. Jimenez, L. Olivares, J.C. Chavez (CCHEN, Chile)
• Monolithic Fuel Plate Development at Argonne National Laboratory
  C.R. Clark, G.C. Knighton, M.K. Meyer, G.L. Hofman (ANL, USA)
• CERCA’s 25 Years Experience in U₃Si₂Fuel Manufacturing
  J.P. Durand, B. Duban, Y. Lavastre and S. De Perthuis (CERCA, France)
• Development of the Fabrication Technology for a HANARO Fuel Rod by the In-Direct Extrusion Method
  J.M. Park, J.Y. Eom, J.Y. Jung, Y.M. Ko, G.S. Joo, C.T. Lee, C.K. Kim, D.S. Sohn (KAERI, Korea)
• An Investigation of the Fabrication Technology for Uranium Foils by Cooling-Roll Casting
  K.H. Kim, S.J. Oh, D.B. Lee, B.C. Lee, C.K. Kim, D.S. Sohn (KAERI, Korea)
• Status of the Back-end Optional Advanced Research Reactor Fuel Development in Korea
  C.K. Kim, Y.S. Lee, D.B. Lee, S.J. Oh, K.H. Kim, H.T. Chae, J.M. Park, D.S. Sohn (KAERI, Korea)

REACTOR CONVERSION ANALYSIS

• Feasibility Studies For LEU Conversion of the WWR-SM Reactor in Uzbekistan Using Pin-Type and Tubular Fuels
  N.A. Hanan, M.M. Bretscher, A.P. Olson, J.E. Matos (ANL, USA)
• Development of IRT-Type Fuel Assembly with Pin-Type Fuel Elements for LEU Conversion of WWR-SM Research Reactor in Uzbekistan
  A. Vatulin, A. Morozov, V. Suprun, I. Dobrikova, V. Mishunin, G. Kulakov (VNIINM, Russia), A. Alexandrov, A. Enin, A. Tkachev (NZChK, Russia)
• Status Report on the HFR Conversion and Relicensing Project
  F.J. Wijtsma (NRG, the Netherlands)
• Preliminary Investigation of the Use of Monolithic U-Mo Fuel in the MIT Reactor
  T. Newton, M.S. Kazimi, E.E. Pilat, Z. Xu (MIT, USA)
• Neutronic Calculations in Core Conversion of the IAN-R1 Research Reactor from MTR HEU to TRIGA LEU Fuel
  J.A. Sarta Fuentes, L. Castiblanco (Distrital University Francisco, Colombia)
• The PLTEMP V2.1 Code
  A.P. Olson (ANL, USA)
• Mathematica as a Versatile Tool to Set-Up and Analyze Neutronic Calculations for Research Reactors
  A. Glaser and C. Pistner (Darmstadt University of Technology, Germany)

SAFETY, SPENT FUEL, AND REGULATORY ISSUES

• Safety Re-Evaluations of the BER II
  H. Krohn, K. Haas, St. Welzel, P. Roedder, R. Lobenstein, A. Poeschke, L. Studen (Hahn-Meitner-Institut, Germany)
• Assessment of Conditions of the Spent Nuclear Fuel Stored in the Stainless Steel Channel-Holders
  M. Pešic, O. Štoic, S. Cupac T. Maksin, N. Dašic (VINCA, Serbia and Montenegro)
• Turkey’s Regulatory Plans for High Enriched to Low Enriched Conversion of TR-2 Reactor Core
  O. Gulol (TAEA, Turkey)
• A MTR Fuel Element Flow Distribution Measurement – Preliminary Results
  W.M. Torres, P. Umbedhaun, D.A. Andrade, J.A.B. Souza (IPEN, Brazil)

SPENT FUEL

• Status of Spent Fuel Storage at the Savannah River Site
  T. Andes , D.W. Bickley, A.S. Busby (WSRC, USA)
• Shipment Security Update
  J. Patterson, C. Anne (NAC, USA)
• The Absolutely Positively Amazing 40 Years of Shipping Spent Fuel
  J. Edlow (Edlow International, USA)
• The Congressional Assault on RERTR
  E. Lyman (UCS, USA)
• RBOF Deinventory Project & HWCTR Oversize Can Disposition
  T. Andes and T. Spieker (WRSC, USA)