Abstracts and Available Papers Presented at the
1999 International RERTR Meeting

The 22^nd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) was held in Budapest, Hungary on October 3-8, 1999. The Abstracts and papers that were presented at this meeting are provided below.

National Programs

• Progress of the RERTR Program in 1999
  A. Travelli
• Moving into the 21^st Century - The United States’ Research Reactor Spent Nuclear Fuel Acceptance Program
  D.D. Huizenga, T.P. Mustin, E.C. Saris, J.E. Reilly
• Status in 1999 of the High Flux Reactor Fuel Cycle
  J. Guidez, A. Gevers, G. Sordon, P.J.M. Thijssen, J.A. Hendriks, F.J. Wijtsma
• The Russian RERTR Program Works Status
  P. Lavreniuk, V. Chernyshov, V. Aden, E. Kartashev, S. Bulkin, V. Likichev,
  A. Aleksandrov, A. Enin, V. Troianov, V. Popov, P. Egorenkov, V. Nasonov
• Status of Reduced Enrichment Program for Research Reactors in Japan
  K. Kaieda, O. Baba, Y. Nagaoka, K. Kanda, Y. Nakagome
• The French Development Program for a UMo Fuel
  R. Romano, J.L. Nigon, A. Languille, E. Le Borgne, H. Freslon 
   

Fuel Development

• Irradiation of Full Size UMo Plates
  H. Vacelet, P. Sacristan, A. Languille, Y. Lavastre, M. Grasse
• Initial Assessment of Radiation Behavior of Very-High-Density Low-Enriched-Uranium Fuels
  G.L. Hofman, M.K. Meyer, J.L. Snelgrove, M.L. Dietz, R.V. Strain, K-H. Kim
• Irradiation Behavior of Uranium-Molybdenum Dispersion Fuel: Fuel Performance Data from RERTR-1 and RERTR–2
  M.K. Meyer, G.L. Hofman, J.L. Snelgrove, C.R. Clark, S.L. Hayes, R.V. Strain, J-M. Park, K-H. Kim
• Prototypic Irradiation Testing of High-Density U-Mo Alloy Dispersion Fuels
  S.L. Hayes, M.K. Meyer, C.R. Clark, J.R. Stuart, I.G. Prokofiev, T.C. Wiencek
• Stable In-Reactor Performances at Low-Temperature of U-10wt.%Mo Dispersion Fuel Containing Centrifugally Atomized Powder
  K-H. Kim, J-M. Park, C-K. Kim, G.L. Hofman, M.K. Meyer, J.L. Snelgrove
• An Investigation on γ-U Phase Stability and Thermal Compatibility of Dispersion Fuel Meats Prepared with Atomized U-16at.%Mo, U-14at.%Mo-2at.%Ru, and U-14at.%Mo-2at.%Os
  C-K. Kim, K-H. Kim, Y-S. Lee, S-B. Park, G.L. Hofman
• Fabrication and Characterization of Atomized U-Mo Powder Dispersed Fuel Compacts for the RERTR-3 Irradiation Test
  J-M. Park, Y-S. Han, K-H. Kim, Y-S. Lee, C-K. Kim
• BWX Technologies Progress with Reduced Enrichment Fuel Production
  B. Pace, E.A. Marinak
• Some Tooling for Manufacturing Research Reactor Fuel Plates
  R.W. Knight
• Melt-Dilute Treatment of Spent Nuclear Fuel Assemblies from Research and Test Reactors
  H.B. Peacock, T.M. Adams, A.J. Duncan, N.C. Iyer
• Scrap Recovery Process for Oxide Fuel Plates
  B.G. Susanto, A. Muchsin, A. Sartono, A. Kadaryono, M.A. Akbar, B. Bull
• High Density Uranium Silicide with Excess Uranium
  A. Suripto, S. Soentono, I.R. Subki, Prayoto, G.L. Hofman
• Calculation of the Evolution of the Fuel Microstructure in UMo Alloys and Implications for Fuel Swelling
  J. Rest, G.L. Hofman, I. Konovalov, A. Maslov
• Progress on DART Code Optimization
  H. Taboada, J. Rest, D. Solis
• Preparation Results for Lifetime Test of Conversion LEU Fuel in Plutonium Production Reactors
  A. Vatulin. Yu. Stetskiy, N. Kukharkin, A. Kalougin, P. Gavrilov, A. Ivanov
   

Core Conversion Studies

• Neutronics Safety Parameters and Transient Analyses for Potential LEU Conversion of the Budapest Research Reactor
  R.B. Pond, N.A. Hanan, J.E. Matos, Cs. Maráczy
• Neutronic Safety Parameters and Transient Analyses for Potential LEU Conversion of the IR-8 Research Reactor
  J.R. Deen, N.A. Hanan, R.S. Smith, J.E. Matos, P.M. Egorenkov, V.A. Nasonov
• Reactor with Different Fuel Assembly Designs with LEU Fuel
  A. Vatulin, Yu. Stetsky, I. Dobrikova, N. Arkhangelsky
• Beryllium Poisoning in the MARIA Reactor
  K. Andrzejewski, T. Kulikowska, M.M. Bretscher, J.E. Matos
• Neutronic Safety Parameters and Transient Analyses for Poland’s MARIA Research Reactor
  M.M. Bretscher, N.A. Hanan, J.E. Matos, K. Andrzejewski, T. Kulikowska
• Fuel Depletion Analyses for the HEU Core of GHARR-1;  Part I:  Actinide Inventory
  S. Anim-Sampong, E.H. K. Akaho, H.O. Boadu, J.D.K. Instiful, S. Osae
• Fuel Depletion Analyses for the HEU Core of GHARR-1;  Part II:  Fission Product Inventory
  S. Anim-Sampong, E.H. K. Akaho, H.O. Boadu, J.D.K. Instiful, S. Osae
• Conversion of the BER II, A Status Report
  H. Krohn, C.-O. Fischer, K. Haas
• Alternative LEU Designs for the FRM-II with Power Levels of 20 - 22 MW
  N.A. Hanan, R.S. Smith, J.E. Matos
• Reduced Enrichment Neutronic Study on High Power Research Reactor
  Peng Feng, Fu Rong
• Reduction of Fuel Enrichment of the WWR-K Research Reactor (Kazakhstan)
  Zh. R. Zhobataev, V.K. Petukhov, F.M. Arinkin, Sh.Kh. Gizatulin, A.V. Vatulin, Yu.A. Stetskiy, I.V. Dobrikova,
  E.P. Ryazantsev, P.M. Egorenkov, V.A. Nasonov
• Minimum Core Configuration with ITR-3M Fuel in the VR-1 Reactor
  K. Matějka, L’. Sklenka, A. Kolros, J. Rataj
• Accuracy of WWR-M Criticality Calculations with Code MCU-RFFI
  Yu.V. Petrov, A.N. Erykalov, M.S. Onegin
• Feasibility Study to Restart the Research Reactor RA with a Converted Core
  M.V. Mataušek, I. Plećaš, N. Marinković
• Pulsed Neutron Source on a Base of LEU Target for the Moscow Meson Factory
  S.F. Sidorkin, I.I. Konovalov, A.A. Maslov, Yu.A. Stetsky, A.V. Vatulin
• South Africa and the RERTR Programme, Current Status – An AEC Perspective
  G. Ball
   

Measurements and Calculations for Converted Reactors

• The New Compact Core Design of the FRG-1
  P. Schreiner, W. Krull
• Thermal Hydraulic and Safety Analyses for Pakistan Research Reactor-1
  I.H. Bokhari, M. Israr, S. Pervez
• Expanding the Storage Capability at ET-RR-1 Research Reactor at INSHASS
  A. Mariy, M. Sultan, M. Khattab
   

Spent Fuel Transportation and Storage

• Transportation 2000, Spent Fuel Transportation Trends in the New Millennium
  D. Blee, J.M. Viebrock, J. Patterson
• Return of TRIGA fuel from the Medical University of Hanover (MHH) to the United States
  G. Hampel, U. Klaus, T. Schmidt
• Status of Storage and Preparations for Shipment of Spent Nuclear Fuel from IRT-2000 Nuclear Research Reactor
  T. Apostolov, M. Vitkova, R. Prodanova, S. Kadalev, E. Moskov, E. Anastasova,
  L. Kinova, A. Stoyanova, V. Anastasov, D. Drenki, R. Atanasova
• Overview of the Spent Nuclear Fuel Storage Facilities at the Savannah River Site
  J. Thomas
• U.S. Department of Energy Operational Experience with Shipments of Foreign Research Reactor Spent Nuclear Fuel
  C.E. Messick, C.D. Massey, T.P. Mustin
• Challenges & Achievements from the “Old” Millennium
  T.A. Shelton, J.M. Viebrock
• Transnucleaire Experience in Research Reactor Fuel Transportation Cycle (Front-End and Back-End)
  C. Anne, J. Galtier
• Resumption of Transport of KUR Spent Fuel from Japan to USA – Very Long-Term Storage and Public Acceptance for Transport
  Y. Nakagome, K. Nishimaki, K. Kanda
• Transportation of Failed or Damaged Foreign Research Reactor Spent Nuclear Fuel
  C.E. Messick, T.P. Mustin, C.D. Massey
• Radiation Exposures Associated with Shipments of Foreign Research Reactor Spent Nuclear Fuel
  C.D. Massey, C.E. Messick, T.P. Mustin
   

Production of Mo-99 from LEU

• Progress in Converting ⁹⁹Mo Production from High -to Low-Enriched-Uranium--1999
  J.L. Snelgrove, G.F. Vandegrift, C. Conner, T.C. Wiencek, G.L. Hofman
• Demonstration of ⁹⁹Mo Production Using LEU Metal-Foil Targets in the Cintichem Process
  G.F. Vandegrift, C. Conner, G.L. Hofman, J.L. Snelgrove, A. Mutalib, B. Purwadi,
  H.G. Adang, L. Hotman, Kadarisman, A. Sukmana, T.J. Dicky, Sryiono,
  A. Suripto, D. Lutfi, D.L. Amin, A. Basiran, A. Gogo, Sarwani, T. Taryo
• Development of Annular Targets for ⁹⁹Mo Production
  C. Conner, E.F. Lewandowski, J.L. Snelgrove, M.W. Liberatore, D.E. Walker,
  T.C. Wiencek, D.J. McGann, G.L. Hofman, G.F. Vandegrift
• Modification of Base-Side ⁹⁹Mo Production Processes for LEU Metal-Foil Targets
  G.F. Vandegrift, R.A. Leonard, S. Aase, J. Sedlet, Y. Koma, C. Conner, C.R. Clark,
  M.K. Meyer
• A Level-Playing Field for Medical Isotope Production: How to Phase Out Reliance on HEU
  A.J. Kuperman