2008 International RERTR Meeting

Abstracts and Available Papers Presented at the Meeting

The “30^th RERTR 2008 International Meeting on Reduced Enrichment for Research and Test Reactors” was held in Washington, D.C. USA from October 5-9, 2008. The available abstracts and papers that were presented at this meeting are provided below.

Welcome to Washington and RERTR-2008

• Welcome to the 30th Annual Meeting
  William Tobey, NNSA
  Yuri Sokolov, IAEA

Invited Presentations - International Perspective on 30 Years of HEU

• S1-1 Reactor Conversion Program: From RERTR to GTRI
  A. Foley, Argonne
• S1-2 Russian HEU Minimization
  Y. Busurin, Rosatom
• S1-3 JAEA’s R&D Activities and Contribution to the RERTR Program
  S. Okada, JAEA
• S1-4 Status of the Work Between Institute of Nuclear Physics of Academy of Sciences of Uzbekistan and National Laboratories of U.S. Department of Energy
  U. Salikhbaev, INP
• S1-5 30 Years of Argentine Collaboration to RERTR Program
  N. Boero, CNEA
• S1-6 Spent Fuel Repatriation from the Budapest Research Reactor
  J. Gado, KFKI
• S1-7 Elimination of the Use of HEU in Australia's Nuclear Facilities
  R. Cameron, ANSTO

Invited Presentations - HEU Minimization Support Programs

• S2-1 An Overview of DOE/NNSA's Global Threat Reduction Initiative
  K. Sheely, NNSA
• S2-2 GTRI Accomplishments and Plans for Removing and Disposing of Civilian HEU
  K. Cummins, NNSA
• S2-3 Fuel Return Programs - Russia
  L. Yungerova, Rosatom
• S2-4 Regulatory Drivers for Reactor Conversion and HEU Minimization
  T. Blount, NRC
• S2-5 IAEA Cooperation with RERTR and Spent Fuel Return Programs: A Retrospective and Future Look
  P. Adelfang, I. Goldman, E. Bradley and D. Jinchuk, IAEA
• S2-6 The Role of HEU Minimization in Reducing the Global Nuclear Dangers - The Norwegian Perspective
  O. Reistad, NRPA W. Beere, IFE
• S2-7 Non-Proliferation Perspectives
  D. Blee, USTC

Invited Presentations - HEU Minimization Programs Overview and Experience

• S3-1 The Focus of the GTRI Reactor Conversion Program in 2009
  P. Staples, NNSA
• S3-2 Status of Conversion Activities at NECSA (South Africa)
  G. Ball, NECSA
• S3-3 Status of GTRI Fuel Development Program
  D. Wachs, INL
• S3-4 The Contribution of Bochvar Institute to the International RERTR Program
  A. Vatulin, VNIINM
• S3-5 Overview of Conversion Plans and Perspective for Miniature Neutron Source Reactors (MNSR)-NIRR-1 Contributions
  S. Jonah, CERT
• S3-6 Ongoing Activities at BR2 in the Framework of Conversion
  E. Koonen, SCK-CEN

Conversion Analysis

• S4-1 Status of Reduced Enrichment Program for Research Reactors in Japan
  T. Ohba, T. Inoue and H. Unesaki
• S4-2 2008 Progress Report on RERTR Activities in Argentina
  S. Balart, D. Cestau, P. Cristini, C. Fernandez, A. Gauna, A. G. Gonzalez, M. Lopes, O. Novara and H. Taboada
• S4-3 Neutronic and Steady State Thermo-Hydraulic Computation of MARIA Reactor with LEU LTA
  K. Andrzejewski, T. Kulikowska, Z. Marcinkowska, W. Mieleszczrnko, K. Pytel, N. A. Hanan and P. L. Garner
• S4-4 Progress in the Analyses of IRT, Sofia LEU Core: Neutronics and Steady-State Thermal-Hydraulic Analyses
  T. G. Apostolov, S. I. Belousov, N. A. Hanan and J. E. Matos
• S4-5 Safety Analysis of LOFA-Type DBA in the WWR-K Reactor at Life Test of Lead Test Assemblies
  F. Arinkin, P. Chakrov, L. Chekushina, Sh. Gizatulin, S. Koltochnik, N. Romanova and A. Shaimerdenov
• PS6-1 Calculation of Argon-41 concentrations for the University of Florida Training Reactor Using Atmospheric Dispersion Modeling Codes: STAC2.1 and CALPUFF
  V. S. Cornelison and G. Sjoden
• PS6-2 Natural Circulation Flow Rate Calculation in PLTEMP/ANL Code
  M. Kalimullah, A. P. Olson, and E. E. Feldman
• PS6-3 Assessing Performance Changes Due to Conversion at FRM-II With Combined Reactor and Virtual-Instrument Simulations
  M. Englert and W. Liebert
• PS6-4 Neutronic Analysis for the Use of Silicide (U3Si2-Al) Fuel Elements in the Peruvian Research Reactor RP-10
  T. Cuya, M. Ravnik and I. R. Llamas Montoya
• PS6-5 The High Performance Research Reactor Fuel Development Hydraulic Test Loop
  W. R. Marcum, B. G. Woods and D. M. Wachs
• PS6-6 Upgrade of Uranium Self-Protection Against Unauthorized Re-Enrichment
  E. F. Kryuchkov, A. N. Shmelev, V. A. Apse, V. A. Yufereva and V. B. Glebov
• PS6-7 An Approach to Quantitative Evaluation of Inherent Proliferation Resistance of Uranium Enriched up to 20% U-235
  E.F. Kryuchkov, A.N. Shmelev, S.V. Masterov, V.B. Glebov and V.A. Apse
• PS6-8 Preliminary Estimations on Conversion of the Research Reactor IRT MEPhI to Reduced Uranium Enrichment: Some Physics and Non-Proliferation Aspects
  E. F. Kryuchkov, V. B. Glebov, V. A. Apse, A. N. Shmelev and M. V. Shchurovskaya
• PS6-9 Transient Analysis for Insertion of LEU LTA in MARIA Reactor
  W. Mieleszczenko, K. Pytel, P. L. Garner, and N. A. Hanan
• PS6-10 NATIRT – Model of the Loss of Flow Transient for Tajoura Research Reactor with LEU Fuel
  F. M. Bsebsu, N. S. Al-Fagaih
• PS6-11 Thermal Hydraulic Design of the First Operating of Tajoura Reactor with LEU Fuel at Thermal Power Level of 5 MW
  F. M. Bsebsu
• PS6-12 Transient Analysis for Prototype MNSR HEU and LEU Core
  G. Ke, Y. Li, Xia Pu and K. Du
• PS6-13 Calculation for Miniature Neutron Source Reactor (MNSR) with LEU
  Y. Li, X. Pu, X. Houhua, P. Da, C. Defu and G. Ke
• PS6-14 Realization of the Core Conversion and Preliminary Study on Core Configuration with only LEU Fuel Assemblies for the DALAT Nuclear Research Reactor
  P. V. Lam, N. N. Dien, V. V. Le, H. T. Nghiem, L. B. Vien and K. C. Nguyen
• S9-1 REBUS and MCODE Burnup Modeling of the MITR for Conversion Studies
  T. Newton, Jr., P. Romano and B. Forget
• S9-2 Progress Made on the University of Missouri Research Reactor HEU to LEU Conversion Feasibility Study
  J. C. McKibben, K. Kutikkad, and L. P. Foyto
• S9-3 A Compressed Core for the Conversion of the NIST Research Reactor to LEU Fuel
  R. E. Williams, W. J. Richards and J. M. Rowe, D. J. Diamond, A. L. Hanson, L. Cheng and A. Cuadra
• S9-4 Comparison of HEU and LEU Fuel Neutron Spectrum in Fuel Element and Flux-Trap Positions
  G. S. Chang
• S9-5 Status of Design for LEU Fuel for the High Flux Isotope Reactor
  R. T. Primm, III, G. Ilas, and C. G. Velit
• S9-6 Optimized Burnable Absorber for the BR2 Reactor
  S. Kalcheva, E. Koonen and B. Guiot
• S14-1 Experimentally Determined Hydraulic Characteristics of HEU and LEU Fuel Assemblies for MARIA Reactor
  W. Mieleszczenko and A. Moldysz
• S14-2 Progress in the Analyses of IRT, Sofia LEU Core: Accident Analyses
  T. G. Apostolov, S. I. Belousov, N. A. Hanan and J. E. Matos
• S14-3 The Impact of Conversion of MNSR to LEU on Neutron Spectrum Parameters
  S. A. Jonah and U. Sadiq
• S14-4 Applicability of WIMS-ANL to Generate Cross Sections for Very High Density UMo Fuel in Proposed MURR LEU Assembly
  B. Dionne, J. Stillman and J. Stevens
• S14-5 Investigation of Multi-Dimensional Effects in Steady-State Thermal Hydraulic Modeling of Core Conversions
  P. L. Garner and N. A. Hanan
• S14-6 U.S. Domestic Reactor Conversion Program
  E. Woolstenhulme

Fuel Development

• S5-1 Research and Development of Very High Density Fuels
  S. Balart, J. D. Hermida, M. López, M. Mirandou, A. G. González
• S5-2 The Status of Testing LEU U-Mo Full-Size IRT Type Fuel Elements and Mini-Elements in the MIR Reactor
  A.L. Izhutov, V.A. Starkov, V.V. Pimenov, V. Ye. Fedoseev, I.V. Dobrikova, A.V. Vatulin, V.B. Suprun, Ye. F. Kartashov, V.A. Lukichev,
  and V. M. Troyanov, A.A. Enin, D.V. Krylov
• S5-3 INVAP's Achievements Using LEU
  J. P. Ordonez
• S5-4 Fresh Fuel Characterization of U-Mo Alloys
  D. E. Burkes, D. M. Wachs, D. D. Keiser, J.-F. Jue, J. Gan, F. Rice, R. Prabhakaran, B. Miller and M. Okuniewski
• S5-5 Swelling of U3Si2 During Irradiation
  Y. S. Kim, G. L. Hofman, J. Rest and A.B. Robinson
• PS10-1 Non-destructive Evaluation Development for Monolithic Fuel Plates
  D. E. Burkes, D. D. Keiser and D. M. Wachs
• PS10-2 Fabrication of Contoured Monolithic Foils
  N. Woolstenhulme, G. Moore, W. Swank, D. Haggard, and J. Wight
• PS10-3 An Investigation on Very Large U-Mo Particle Arrayed Plate Type Fuel Available for High U-density of More than 8 g-U/cc
  C. K. Kim, H. J. Ryu, S. J. Jang, S. J. Oh and G. H. Choi
• PS10-4 Fabrication of MTR-Sized High Loaded U-Mo Dispersion Fuel Plates
  M. J. Nilles and J. M. Wight
• PS10-5 Powder Production of Uranium - Molybdenum - Metal Alloys Applying Hydride - Dehydride Methodology
  L. Olivares, J. Marin, J. Lisboa and H. Pesenti
• PS10-6 Differential Thermal Analysis and Scanning Calorimetry Applied to the Study of the Stability of Some Gamma-UMo Based Alloys with Oxygen
  F. Branco Vaz de Oliveira, H. Gracher Riella and E. Urano Fontenelle de Carvalho
• PS10-7 PIE Results of the KOMO-3 Fuels and the Future Irradiation Test Plan
  J. M. Park, H. J. Ryu, Y. S. Lee, S. J. Oh, C. K. Kim , B. O. Yoo, Y. H. Jung, C. G. Seo, C. S. Lee and H. T. Chae
• PS10-8 Small-Scale Specimen Testing of Monolithic U-Mo Fuel Foils
  R. Prabhakaran, D. Burkes, D. Wachs, J. Cole and I. Charit
• PS10-9 Analysis of Fission Gas Bubble Swelling in U-Mo Fuel
  J. Rest, G. L. Hofman and Y. S. Kim
• PS10-10 Safety Basis Determination for U-Mo Monolithic and Dispersion Fuel Plates
  F. J. Rice, D. M. Wachs, P. A. Demkowicz, L. T. Cole
• PS10-11 U.S. RERTR Fuel Development Post Irradiation Examination Techniques
  A. B. Robinson
• PS10-12 Post Irradiation Examination of Modified Interface High Density Monolithic Fuel
  A. B. Robinson, D.E. Burkes and D. M. Wachs
• PS10-13 Scrap Recovery Operations in the Fuel Fabrication Capacity
  D. Stepinski, L. Maggos, J. Swanson, J. Stevens and G. Vandegrift
• PS10-14 Testing and Acceptance of Fuel Plates for RERTR Fuel Development Experiments
  J. M. Wight, G. A. Moore, S. C. Taylor, N. E. Woolstenhulme and S. T. McCormick
• PS10-15 Radiation Effects on the Microstructure Stability of RERTR Fuels
  B. D. Miller, J. Gan, T. R. Allen, D. D. Keiser and D. M. Wachs
• PS10-16 Y-12’s Role in Advanced Fuel Development
  R. Johnson, A. DeMint, and J. Gooch
• PS10-17 The Electron-Microscopy Study of Barrier Coatings on the U-9% Mo Fuel Irradiated to 60% Burn Up
  O. A. Golosov, S. А. Аverin, M. S. Lyutikova, V. V. Shushlebin, V. М. Тroyanov, B. V. Popov, and G. А. Birzhevoy
• S12-1 The Role of Friction Bonding in the RERTR-10B Experiment
  D. E. Burkes, N. P. Hallinan, M. D. Chapple, and J. Chapman
• S12-2 Characterization of the Interaction Layer Between Decomposed UMO7 and Aluminum Using Micro-Focused XRD on a Single Particle
  H. Palancher, E. Welcomme, C. Sabathier, P. Martin, F. Mazaudier, C. Valot, S. Dubois, R. Tucoulou and P. Lemoine
• S12-3 Characterization of Si-Rich Layers in As-Fabricated and As-Irradiated RERTR Dispersion Fuel Plates: Recent Results
  D. D. Keiser, J. F. Jue J. Gan, A. B. Robinson and B. D. Miller
• S13-1 Irradiation Behavior of Atomized and Ground U(Mo) Dispersion Fuel
  A. Leenaers, S. Van Den Berghe, M. Ripert, J. Noirot, M.-C. Anselmet, P. Lemoine, A. Röhrmoser and W. Petry
• S13-2 Post-Irradiation Analysis of U-Mo Miniplates Tested to Date
  G. L. Hofman, Y. S. Kim, J. Rest, T. Totev and A. B. Robinson
• S13-3 LEU U3SI2 Fuel Manufacturing for MARIA Reactor (Poland)
  P. Colomb, L. Halle, G. Krzysztoszek, W. Mieleszczenko, F. J. Blom, F. Roelofs and C. J. J. Beemsterboe
• S13-4 Update on Integral Performance Modeling of RERTR Experimental Fuel Plates
  P. Medvedev and Y. S. Kim
• S13-5 Advances in the Characterization of Annealed Atomized UMo/Al Particles Using Synchrotron Radiation
  H. Palancher, E. Welcomme, P. Martin, C. Valot, P. Bleuet, R. Tucoulou and P. Lemoine
• S16-1 Analyses on Interaction Products of U-Mo/Al-Si Dispersion Fuel for an Estimation of the Required Silicon Content
  H. J. Ryu, J. M. Park, C. K. Kim and Y. S. Kim
• S16-2 Monolithic Fuel Fabrication Process Development at the INL
  G. A. Moore, F. J. Rice, N. E. Woolstenhulme, W. D.Swank, D. C. Haggard, J. F. Jue, B. H Park, S. E. Steffler, N. P. Hallinan, M. D. Chapple, and D. E. Burkes
• S16-3 Production of Depleted U-10 Wt.% Mo Foils
  T. Muth and B. Oakley

Mo-99 Production

• S7-1 Mo-99 Production and the Need for New Sources of Radionuclides for Use in Nuclear Medicine
  R. W. Brown
  
• S7-2 Status of NAS Study on Mo-99
  K. Crowley
• S7-3 HEU and LEU Cost Comparison in the Production of Molybdenum-99
  D. M. Cestau, P. R. Cristini, E. Carranza, J. Cestau, R. Bavaro, M. Bronca, R. Centurión and A. Novello
• S7-4 Status of the Chilean Implementation of the Modified Cintichem Process for Fission 99Mo Production Using LEU
  R. Schrader, J. Klein, J. Medel, J. Marín, J. Lisboa, L. Birstein, L. Ahumada, M. Chandía, R. Becerra, X. Errazu, C. Albornoz, G. Sylvester, and J.C. Jiménez
  
• S7-5 Overview of Babcock & Wilcox Medical Isotope Production System (MIPS)
  E. Reynolds
• S7-6 Overview of Argonne Progress Related to Implementation of Mo-99 Production by Use of a Homogeneous Reactor
  G. Vandegrift, S. Chemerisov, J. Fortner, A. Gelis, J. Jerden, D. Stepinski, A. Zeigler, and A. Bakel
• S8-1 Overview of Argonne Progress Related to Implementation of the LEU-Modified Cintichem Process
  A. Bakel, A. Leyva, T. Wiencek, A. Hebden, K. Quigley, J. Falkenberg, L. Hafenrichter and G. Vandegrift
• S8-2 Fostering New Sources of Mo-99 for International Nuclear Medicine Needs – the Contribution of the IAEA Coordinated Research Project on Molybdenum-99 Production from LEU or Neutron Activation
  I. Goldman, N. Ramamoorthy and P. Adelfang
• S8-3 LEU Dispersion Fuel Target Manufacturing at AREVA-CERCA
  C. Jarousse and G. Bourdat
• S8-4 ROMOL-99: A New Innovative Small-Scale LEU-Based Mo-99 Production Process
  G. Beyer, R. Muenze, D. Novotny, M. Ahmad, M. Jehangir
• S8-5 Engineering Design of LEU Foil Based Target for High Volume Production of Mo-99
  G. L. Solbrekken, A.S. El-Gizawy and C. Allen
• PS15-1 Design of Remotely Operated Disassembly Device for Annular Targets During Production of Mo-99
  A. S. El-Gizawy, J. Cardona, J. L. McCord and C. W. Allen
• PS15-2 Predictive Modeling of Solution Chemistry in an Aqueous Homogeneous Reactor Used for Mo-99 Production
  J. L. Jerden Jr. and G. Vandegrift
• PS15-3 Hydrodynamic Measurements in Irradiation Position for Mo-99 Production LEU Target
  G. L. Solbrekken, J. Scott and C. Allen
• PS15-4 Status and Progress of Foil and Target Fabrication Activities for the Production of Mo-99 from LEU
  T.C. Wiencek, G. F. Vandegrift, A. Bakel, A. A. Leyva and A.S. Hebden
• PS15-5 Mo-99 Recovery from Aqueous-Homogeneous-Reactor Fuel—Behavior of Termoxid Sorbents
  A. Ziegler, D. Stepinski, J. Krebs, S. D. Chemerisov, A. Bakel and G. Vandegrift
• PS15-6 Radiolysis Effects on the Composition and Rate of Gas Generation in an Aqueous Homogeneous Reactor
  S. Chemerisov, A. Gelis, A. Bakel and G. Vandegrift
• PS15-7 Radiolysis Effects on Molybdenum Oxidation State and Recovery from Aqueous-Homogeneous-Reactor Fuel
  A. Gelis, S. Chemerisov, A. Bakel and G. Vandegrift
• PS15-8 Development of Robust Technology for Assembling Annular Targets Carrying LEU Foils for Production of Mo-99
  A. S. El-Gizawy, J. Cardona, C. W. Allen and G. F. Vandegrift
• PS15-9 An Outlook on New Sources of Mo-99 and other Medical Radionuclides
  R. W. Atcher, R. W. Brown and J. P. Norenberg

Minimization, Transportation and Fuel Disposition

• S11-1 Exportation Campaign of Spent Nuclear Fuel from the RA-6 Reactor
  O. Calzetta, C. Díaz, G. Facchini, C. Fernandez, O. Novara, F. Orlando, M. Ratner, N. Rico and H. Taboada
• S11-2 Return of HEU Fuel from the Portuguese Research Reactor
  J.G. Marques, N. P. Barradas, A. Kling, A. R. Ramos, C. Anne and V. Garcia
• S11-3 The U.S. Role in Promoting HEU Minimization
  A. Loukianova and C. Hansell
• S11-4 HEU Guidelines, Codes of Conduct, Resolutions, and Other Measures to Promote HEU Minimization
  C. Hansell
• S11-5 The United States Foreign Research Reactor (FRR) Spent Nuclear Fuel (SNF) Acceptance Program: 2008 Update
  C. Messick, J. Taylor and J. D. Chamberlin