Abstracts and Available Papers Presented
at the 1996 International RERTR Meeting

The 1996 International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) was sponsored by the Korea Atomic Energy Research Institute and the International Atomic Energy Agency and was held in Seoul, Korea, on 6-10 October 1996. The abstracts and available papers that were presented at this meeting are provided below. An (A) after the title of a paper indicates that only the abstract is currently available. An (A,P) after the title indicates that both the abstract and the paper are available for downloading.

National Programs

• Status and Progress of the RERTR Program (A,P)
  A. Travelli, Argonne National Laboratory
• The United States Policy Inititatives in Promoting the RERTR Program (A,P)
  D.G. Huizenga, United States Department of Energy
• The Russian RERTR Program Works Status (A)
  V.G. Aden, B.A. Gabaraev, E. Kartashev, S.Y. Bulkin, and V.A. Lukichev, Research and Development Institute of Power Engineering
  N.V. Arkhangelsky, Ministry of Atomic Energy, Russian Federation
• RERTR Program, French Status in 1996 (A)
  J. Guidez and A. Ballagny, CEA Saclay, France
• Status of Reduced Enrichment for Research Reactors in Japan (A)
  K. Kanda and Y. Nakagome, Kyoto University Research Reactor Institute
  Masahiko Isshiki, Osamu Baba and Harumichi Tsuruta, Japan Atomic Energy Research Institute, Japan

Fuel Development, Testing and Evaluation

• Development of Very-High Density Fuels by the RERTR Program (A,P)
  J.L. Snelgrove, G.L. Hofman, C.L. Trybus, and T.C. Wiencek, Argonne National Laboratory, U.S.A.
• Status of Research Reactor Fuel Development in KAERI (A)
  Chang-Kyu Kim, Woo-Seok Ryu, Jong-Man Park, Don-Bae Lee, Ki-Hwan Kim, and Il-Hyun Kuk, Korea Atomic Energy Reserch Institute, Korea
• Babcock & Wilcox Fabrication Experience with KAERI Spherical Fuel (A)
  L.E. Todd and B.W. Pace, Babcock & Wilcox, U.S.A.
• LEU Fuel Development at CERCA, Status as of October 1996 (A)
  J.P. Durand, G. Olagnon, P. Colomb, Y. Lavastre, and M. Grasse,CERCA
  H. Noel and V. Queneau, CNRS, France
• Aluminum-U3Si2 Interdiffusion and Its Implications for the Performance of Fuel Operating at Higher Temperatures and Fission Rates (A,P)
  G.L. Hofman, J. Rest, J.L. Snelgrove, and T. Wiencek, Argonne National Laboratory
  S. Koster an Goos, Cornell University, U.S. A.
• Fabrication Develpment of the Plate Fuel for Indian Research Reactors (A)
  G.J. Prasad, K.N. Mahule, J.K. Ghosh, C. Ganguly, D.S.C. Purushotham, and M.S. Ramakumar, Bhabha Atomic Research Centre, India
• Results of Fuel Element Fabrication on the Basis of Increased Concentration Dioxide Fuel for Research Reactors (A)
  A.B. Aleksandrov, V.L. Afanasiev, and A.A. Enin, Novosibirsk Chemical Concentrates Plant, Inc.
  V.B. Suprun, All-Russian Scientific Research Institute for Inorganic Materials, Russian Federation
• Development of High Loading U-Mo Alloy Fuel by Centrifugal Atomization (A)
  Ki Hwan Kim, Don Bae Lee, Chang Kyu Kim, and Il Hyun Kuk, Korea Atomic Energy Research Institute, Korea
  G. L. Hofman, Argonne National Laboratory, U.S.A.
• Fabrication Experience, Inspection and Irradiation Programme for 2 LEU Silicide Elements Fabricated by UKAEA (Dounreay,UK) for Irradiation in HFR (Petten, NL) (A)
  P. Cartwright, United Kingdom Atomic Energy Authority, UK
  J. Markgraf, Joint Research Centre of the Institute for Advanced Materials of the European Commission
  F.J. Wijtsma, Netherlands Energy Research Foundation, The Netherlands
• Calculated-Experimental Investigation of Fuel Elements with High-Density Fuel (A)
  A. Vatulin, All-Russian Scientific Research Institute for Inorganic Materials, Russian Federation
• Irradiation-Behaviour Modelling of Uranium Oxide-Aluminum Dispersion Fuel (A,P)
  G.L. Hofman, J. Rest, and J.L. Snelgrove, Argonne National Laboratory, U.S.A.
• Relative Neutronic Performance of Proposed High-Density Dispersion Fuels in Water-Moderated and D2O Reflected Research Reactors (A,P)
  M.M. Bretscher, J.E. Matos, and J.L. Snelgrove, Argonne National Laboratory, U.S.A.
• Irradiation of a Uranium Silicide Fuel Element Prototype in RA-3 Reactor (A)
  R. Calabrese, G. Estryk, and C. Notari, Comision Nacional de Energia Atomica, Argentina

Research Reactor Analysis

• LEU Conversion and Assessment Status of U.S. Research and Test Reactors (A,P)
  J.E. Matos, Argonne National Laboratory, U.S.A.
• An Alternative LEU Design for the FRM-II (A,P)
  N.A. Hanan, S.C. Mo, R.S. Smith and J.E. Matos, Argonne National Laboratory, U.S.A.
• HANARO Nuclear Commissioning Test (A)
  Byung Jin Jun, Hark Rho Kim and Ji Bok Lee, Korea Atomic Energy Research Institute, Korea
• Measurement of Thermal and Fast Neutron Flux Distribution in Initial Core of HANARO (A)
  Byung Chul Lee, Hark Rho Kim, Byung Jin Jun, and Ji Bok Lee, Korea Atomic Energy Research Institute, Korea
• Program of Converting IEA-RI Brazilian Research Reactor form HEU to LEU (A)
  J.A. Perotta and P.E. de Oliveira Lainetti, Instituto de Pesquisas Energeticas e Nucleares, Brazil
• Enrichment Reduction Programme on Research Reactor LVR-15
  and Training Reactor VR-1 In Czech Republic (A)
  E. Listik, Nuclear Research Institute in Rez
  K. Matejka, Czech Technical University in Prague, Czech Republic
• A Concept of LEU Pool Type High Flux Research Reactor With Solid Coolant (A)
  V. Artamkin and J. Chikhladze, Research and Development Institute of Power Engineering, Russian Federation
• A Comparison of the PARET/ANL and RELAP5/MOD3 Codes for the Analysis of IAEA Benchmark Transients (A,P)
  W.L. Woodruff, N.A. Hanan, R.S. Smith and J.E. Matos, Argonne National Laboratory, U.S.A.
• Verification of Computer Codes for Dynamic Processess in Nuclear Reactors against Experiments at Loop Facility of IGR-1 Pulse Reactor (A)
  V.G. Aden, Yu.A. Dolgov, E. Karassev, E.F. Kartashev, and V.D. Pugach, Research and Development Institute of Power Engineering, Russian Federation
• A Procedure for Searching the Equilibrium Core of a Research Reactor (A)
  B. Arbie and L.P. Hong, Center for Multipurpose Reactor, Pispiptek Complex, Serpong
  Prayoto, Gadjah Mada University, Yogyakarta, Indonesia
• Criticality Safety Analysis for MPR Storage Facility (A)
  A.M. Hathout and E. Amin, National Centre for Nuclear Safety and Radiation Control, Egypt

Mo-99 Production From LEU Fission

• Irradiation Tests of Mo-99 Isotope Production Targets Employing Uranium Metal Foils (A,P)
  G.L. Hofman, T.C. Wiencek, E.L. Wood, and J.L. Snelgrove, Argonne National Laboratory, U.S.A.
  A. Suripto, H. Nasution, D. Lufti-Amin, and A Gogo, Badan Tenaga Atom National, Indonesia
• Progress in Chemical Treatment of LEU Targets by the Modified Cintichem Process (A,P)
  D. Wu and S. Landsberger, University of Illinois at Urbana-Champaign
  G.F. Vandegrift, Argonne National Laboratory, U.S.A.
• Progress in Alkaline Peroxide Dissolution of Low-Enriched Uranium Metal and Silicide Tagets (A,P)
  L. Chen, D. Dong, B.A. Buchholz, and G.F. Vandegrift, Argonne National Laboratory
  D. Wu, University of Illinois at Urbana-Champaign, U.S.A.
• Progress in Dissolving Modified LEU Cintichem Targets (A,P)
  R.A. Leonard, L. Chen, C.J. Mertz, and G.F. Vandegrift, Argonne National Laboratory, U.S.A.

Fuel Cycle

• Supply of Enriched Uranium for Research Reactors (A)
  H. Mueller and J. Laucht, NUKEM GmbH, Germany
• Back-end of the Research Reactor Fuel Cycle(A)
  G. J. Gruber, NUKEM GmbH, Germany
• Status and Perspectives of FRG-1 after Conversion to LEU (A)
  W. Krull and W. Jager, GKSS, Germany
• MTR Spent Fuel Management for a Steady Back-End (A)
  Ph. de l'Epine, COGEMA, France
• French Experience in Research Reactor Fuel Transportation (A)
  D. Raisonnier, Transnucleaire, France
• Nuclear Mass Inventory, Photon Dose Rate, and Themal Decay Heat of Spent Research Reactor Assemblies (A,P)
  R.B. Pond and J.E. Matos, Argonne National Laboratory, U.S.A.
• Reprocessing of LEU Silicide Fuel at Dounrey (A)
  P. Cartwright, UKAEA, UK
• Guidance for Shipping Foreign Research Reactor Spent Fuel to U.S.A. (A)
  A. Zeitoun, J. Williams and K. Brown, Science Applications International Corporation, USA
  K. Chacey, Office of Spent Fuel Management, Department of Energy
• Studsvik's Implementation of the DOE Spent Fuel Return Program: The US Perspective (A)
  S. Grover and R.C. Bowser, Studsvik, Incorporated, USA
• NAC International Dry Spent Fuel Transfer Technology (A)
  T.A. Shelton, J.P. Malone and J.R. Patterson, NAC International, USA
• Final Disposition of MTR Fuel (A)
  E.B. Jonsson, Studsvik Nuclear AB, Sweden
• Background and Planning Requirements for Spent Fuel Shipments to DOE (A)
  N. Ravenscroft, Edlow International Co., U.S.A.