Abstracts and Available Papers Presented at the
2000 International RERTR Meeting

The 23^rd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) was held in Las Vegas, Nevada on October 1-6, 2000. The abstracts and available papers that were presented at this meeting are provided below.

In conjunction with the meeting, the Yucca Mountain Project provided a tour of the Yucca Mountain site. The U.S. Department of Energy is studying Yucca Mountain, Nevada to determine if it is a suitable place to build a geologic repository for U.S. commercial and defense spent nuclear fuel and high-level radioactive waste.
Yucca Mountain Home page

National Programs

• Welcome Address
  T. Dedik, U.S. Department of Energy, USA
• Status and Progress of the RERTR Program in the Year 2000
  A. Travelli, Argonne National Laboratory, USA
• A Continuing Success – The U.S. Research Reactor Spent Nuclear Fuel Acceptance Program
  T.P. Mustin, M. Clapper, and J.E. Rielly U.S. Department of Energy, USA
• Technological Irradiation Reactors and RJH Progress Status
  A. Ballagny, S. Frachet, M. Rommens, B. Guigon, C.E.A., France
  J.L. Minguet, J.P. Dupuy, C. Leydier, Technicatome, France
• Twenty Years of RERTR in Russia: Past, Present, and Future
  N. Arkhangelsky, Minatom of Russia, Russia
• Status of RERTR in Japan
  K. Kanda, Y. Nakagome, Kyoto University, Japan
  K. Kaieda, H. Takahashi and K. Shimizu, Japan Atomic Energy Institute, Japan
• RERTR Activities in Argentina
  P. Adelfang, L. Alvarez, N. Boero, R. Calabrese, M. De La Fuente, P. Echenique,
  M. Markiewicz, E. Pasqualini, A. Pérez, A. Piazza, G. Ruggirello, H. Taboada
  Comisión Nacional de Energía Atómica, Argentina
• Status in 2000 of the High Flux Reactor Fuel Cycle
  J.S. Guidez, A. Gevers, European Communities JRC, The Netherlands
  F.J. Wijtsma, P.J.M., Thijssen, J.A. Hendriks, NRG, The Netherlands
• The Conversion to LEU of a Mo-99 Commercially Producing Reactor: SAFARI of South Africa
  W.E. Stumpf, AP Vermaak, G Ball, NECSA, South Africa
• A Conversion Development Program to LEU Targets for Medical Isotope Production in the Maple Facilities
  G. Malkoske, MDS Nordion, Canada

Fuel Development

• Observations on the Irradiation Behavior of U-Mo Alloy Dispersion Fuel
  G.L. Hofman, M.K. Meyer, Argonne National Laboratory, USA
   J.M. Park, Korea Atomic Energy Center, South Korea
• U-Mo Fuel Development at BWX Technologies, Inc.
  B. Pace, G. Gale, BWX Technologies, Inc. USA
• Status as of October 2000 of U-Mo Development Program
  H. Vacelet (CERCA), A. Languille (CEA), E. Le Borgne (Technicatome), J.M. Hamy (Framatome), J.L. Guillet (Cogema), France
• Irradiation Behavior of U-Mo Dispersion Fuel:  Fuel Performance Data from RERTR-3
  M.K. Meyer, G.L. Hofman, R.V. Strain, C.R. Clark, and J.R. Stuart
  Argonne National Laboratory, USA
• Research Reactor Fuel Development at AECL
  D.F. Sears and N. Wang, Atomic Energy of Canada Limited, Canada
• Irradiation Testing of Intermediate and High Density U-Mo alloy Dispersion Fuels to High Burnup
  S. L. Hayes, C. R. Clark, J. R. Stuart, M. K. Meyer, T. C. Wiencek, J. L. Snelgrove and G. L. Hofman, Argonne National Laboratory, USA
• Fabrication of Atomized U-Mo Dispersion Rod Type for Irradiation Test Related to the Qualification
  C.K. Kim, H.J. Ryu, J.M. Park, K.H. Kim, H.R. Kim, K.H. Lee
  Korea Atomic Energy Research Institute, Korea
• Development of the Method of High Density Fuel Comminution by Hydride-Dehydride Processing
  M.I. Solonin, A.V. Vatulin, Y.A. Stetsky, Y.I. Trifonov, B.D. Rogozkin, Bochvar Institute, VNIINM, Russia
• U-Mo Alloy Power Obtained by a Hydride-Dehydride Process
  S. Balart, P. Bruzzoni, M. Granovsky, L. Gribaudo, J. Hermida, J. Ovejero, G . Rubiolo, E. Vicente, Comisíon Nacional De Energía Atómica, Argentina
• Low-Enriched Uranium-Molybdenum Fuel Plate Development
  T. C. Wiencek and I. G. Prokofiev, Argonne National Laboratory, USA
• An Investigation on the Fuel/Matrix Reaction Behaviors of Atomized U-Mo/Al Dispersion Fuels Prepared by Centrifugal Atomization
  K.H. Kim, H.J. Kwon, J.S. Lee, H.J. Ryu, J.M. Park, and C.K. Kim
  Korea Atomic Energy Research Institute, Korea
• Characteristic Test of Silicide Fuel Core in JRR-3M
  M. Yagi, S. Wada, Y. Murayama and M. Takeuchi, Japan Atomic Energy Research Institute, Japan
• Preparation for In-Pile Tests of a LEU New Type Fuel Element
  A. Vatulin, Y. Stetsky, I. Dobrikova, Bochvar Institute, VNIINM, Russia

Fuel Testing

• LEU WWR-M2 Fuel Assemblies Burnable Test
  K.A. Konoplev, Petersburg Nuclear Physics Institute, Russia
• Testing of the IRT-4M Type FA with LEU U02-Al Fuel in the WWR-CM Reactor
  P.M. Egorenkov, Kurchatov Institute, Russia
• LEU Fuel Fabrication Program for the RECH-1 Reactor, Status Report
  J.C. Chavez, Comision Chilena De Energia Nuclear, Chile
• LEU Fuel Fabrication Program for the RECH-1 Reactor, Status Report
  J.C. Chavez, Comision Chilena De Energia Nuclear, Chile

Fuel Modeling

• Fundamental Properties of Fuel – Determining Its Behavior Under Irradiation
  I. Konovalov, Bochvar Institute, VNIINM, Russia
• A Theoretical Model for the Irradiation-Enhanced Interaction Between Al and Uranium-Alloy Fuels
  J. Rest, Argonne National Laboratory, USA
• Fast Dart: A New Friendly and Quick Version of Dart Code
  H.H. Taboada, Comisíon Nacional De Energía Atómica, Argentina, J. Rest, Argonne National Laboratory, USA

Conversion Studies

• Neutronic Feasibility Studies for LEU Conversion of the HFR Petten Reactor
  N.A. Hanan, J.R. Deen, and J.E. Matos, Argonne National Laboratory, USA
• A Neutronic Feasibility Study for LEU Conversion of the SAFARI-1 Reactor
  R. B. Pond, N. A. Hanan and J. E. Matos, Argonne National Laboratory, USA
• Neutronic Feasibility Studies Using U-Mo Dispersion Fuel (9Wt%Mo, S.0g/Ucm³) for LEU Conversion of the MARIA (Poland), IR-8 (Russia), and WWR-SM (Uzbekistan) Research Reactors
  M. M. Bretscher, J. R. Deen, N. A. Hanan, and J. E. Matos, Argonne National Laboratory, USA
• Status of REBUS Fuel Management Software Development for RERTR Applications
  A. Olson, Argonne National Laboratory, USA
• Reactivity Effect of Interchanging Positions of Poisoned Beryllium Blocks in the MARIA Reactor
  K. Andrzejewski, T. Kulikowska, Institute of Atomic Energy, Poland
• A Neutronic Feasibility Study for LEU Conversion of the WWR-M Reactor at Gatchina
  Yu. V. Petrov, A. N. Erykalov and M. S. Onegin, Petersburg Nuclear Physics Institute, Russia
• Optimum Fuel Management for the German Research Reactor Using MCNP
  R. Nabbi, G. Thamm, J. Wolters, Forschungzentrum Jeulich, ZFR, Germany
• Plant Safety Review From Mass Critical Accident
  B.G. Susanto, PT Batan Teknologi (Persero), Indonesia

Conversion Experience

• The Rhode Island Nuclear Science Center Conversion from HEU to LEU Fuel and Efforts to Upgrade from 2 MW to 5 MW
  T.N. Tehan, Rhode Island Atomic Energy Commission, USA
• Modification of the Rhode Island Nuclear Science Center LEU Core to Increase Fluxes for Boron Neutron Capture Therapy Study
  S. C. Mo, R. S. Smith and J. E. Matos, Argonne National Laboratory, M.J. Davis and T. Tehan, Rhode Island Atomic Energy Commission, USA
• Safety Analysis of an Irradiation Device for ⁹⁹Mo Production in RA-3 Reactor
  A.M. Lerner, M. Madariaga, R. Waldman, Autoridad Regulatoria Nuclear, Argentina
• Fuel Element Burnup Determination in HEU-LEU Mixed TRIGA Research Reactor Core
  T. Žagar and M.Ravnik, Institute “Jožef Stefan”, Slovenia
• Demonstration of Core Neutronic Calculations for Research and Training Reactors via SCALE4.4
  Y. Çeçen, M. Tombakoğlu*, Hacettepe University, Turkey, S. Köse, A. Yılmazer, Turkish Atomic Energy Authority, Turkey, M. Sağlam Framatome Cogema Fuels, USA

New Conversions and Reactors

• HEU/LEU Conversion of BER II Successfully Finished
  K. Haas, C.-O. Fischer, H. Krohn, Hahn-Meitner-Institut, Berlin GmbH, Germany
• FRM-II Conversion Revisited
  A. Glaser, C. Pistner, W. Liebert, Darmstadt University of Technology, Germany
• Nuclear Liability and Research Reactor Fuel, A Plant-Supplier's View
  H.J. Roegler, Siemens Nuclear Power GmbH, Germany

Transportation

• Pre-Shipment Preparations at the Savannah River Site-WSRC’s Technical Basis to Support DOE’s Approval to Ship
  J.E. Thomas, D.W. Bickley, and E.R. Conatser, Westinghouse Savannah River Company, USA
• Package Licensing in Support of the U.S. DOE Foreign Research Reactor Spent Nuclear Fuel Acceptance Program
  B.K. Chambers and Maureen Clapper,
  U.S. Department of Energy, USA
• New CERCA Transport Container
  G. Harbonnier, F. Obadia, CERCA, France, and C. Anne (Transnucléaire Paris),
• Inspection Experience with RA-3 Spent Nuclear Fuel Assemblies at CNEA’s Central Storage Facility
  Oscar Novara and Jose LaFuente,
  Comision Nacional de Energia Atomica, Argentina,
  Steve Large and Trent Andes,
  Westinghouse Savannah River Company, USA, Charles Messick, U.S. Department of Energy, USA
• The Operation and Logistic Experience on Transportation of Brazilian Spent Fuel to the USA
  J.R. Maiorino and R. Frajndlich IPEN, Brazil, M. Mandla, NCS, Germany, W. Bensberg, A. Renger, and K. Grabow, GNS, Germany

Mo-99 Production

• Production of Mo-99 From LEU Targets – Acid Side Processing
  C. Conner, J. Sedlet, T. C. Wiencek, D. J. McGann, G.L.Hofman, G. F. Vandegrift, and J. L. Snelgrove,
  Argonne National Laboratory, USA,
  A. Mutalib, A. H. Gunawan, H. G.Adang, H. Lubis, K. Wisnukaton, Kadarisman, A. Sukmana, Sriyono, B. Purwadi, D. T. Jatmiko, A. Suripto, D. L. Amin, A. Basiran, Martoyo, Sarwani, and T. Taryo,
  Indonesian National Nuclear Energy Agency, Indonesia
• Low Enrichment Mo-99 Targets Development Program at ANSTO
  T.M. Donlevy, P.J. Anderson, G. Storr, G. Yeoh, D. Beattie, M. Deura, D. Wassink, B. Braddock, W. Chant., Australian Nuclear Science & Technology, Australia
• Production of Mo-99 From LEU Targets -  Base Side Processing
  G.F. Vandegrift, Y. Koma, H. Cols, C. Conner, S. Aase, M. Peter, D. Walker, R.A. Leonard, and J.L. Snelgrove, Argonne National Laboratory, USA
• Targets Development of Low Enrichment for the Production of ⁹⁹Mo Fission
  C. Kohut, M. De La Fuente, P. Echenique, D. Podesta, P. Adelfang
  Comisíon Nacional De Energía Atómica, Argentina
• Mo-99 From Low Enriched Uranium
  H.J. Cols , P.R. Cristini , A.C. Manzini
  Comisíon Nacional De Energía Atómica, Argentina