2006 International RERTR Meeting

Abstracts and Available Papers Presented at the Meeting

The 28^th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) was held October 29 through November 2, 2006 at the Southern Sun Cape Sun Hotel in Cape Town, Republic of South Africa. The available abstracts and papers that were presented at this meeting are provided below.

Welcome to South Africa

• Welcome
  R. Adam, CEO of Necsa

Opening Programmatic Remarks

• S1-1 Overview of GTRI Strategic Policy
  A. Bieniawski
• S1-2 Opening Remarks - IAEA
  H. Forsström

Reduced Enrichment National Programs

• S2-1 The Office of Global Threat Reduction's (GTRI) Reactor Conversion Program
  P. Staples
• S2-2 SAFARI-1: Adjusting Priorities During the LEU Conversion Program
  C. Piani
• S2-3 IAEA Assistance Programme for Research Reactors: Fuel Conversion, Repatriation and Management of Fresh and Irradiated Fuel: 2 Successul Years of Reducing Nuclear Threats
  A. Atger
• S2-4 Status of Reduced Enrichment Program for Research Reactors in Japan
  M. Kinase, H. Sagawa, Y. Nakagome, H. Unesaki
• S2-5 Progress on RERTR Activities in Argentina
  S. Balart, O. Calzetta, P. Cristini, J. Garces, A. Gauna, A. Gonzalez, J. Hermida, E. Pasqualini, H. Taboada

HEU Minimization

• S3-1 Status and Progress of IAEA Activities on Research Reactor Fuel Conversion and Spent Fuel Return Programmes in the Years 2005-2006
  P. Adelfang, I. Goldman, A. Soares, E. Bradley
• S3-2 HEU Minimization: The Technical-Political Nexus
  C. Cheun, S. Parrish, W. Potter, E. Sokova
• S3-3 Impediments and Opportunities for a Global Cleanout of HEU in the Civilian Nuclear Sector - the Oslo Perspective
  O. Harbitz and O. Reistad
• S3-4 Global Threat Reduction Initiative Russian Nuclear Material Removal Progress
  I. Bolshinsky
• S3-5 The United States Foreign Research Reactor (FRR) Spent Nuclear Fuel (SNF) Acceptance Program: 2006 Update
  C. Messick, J. Taylor

Reactor Conversion Experience

• S4-1 Calculated and Measured Parameters of the Tajoura Critical Facility Fueled with LEU
  O. Abuzid Abulgasem, N. Hanan, A. Ajaj
• S4-2 Full Conversion of 14 MW TRIGA Research Reactor at Institute for Nuclear Research Pitesti Romania
  M. Ciocanescu, C. Toma, M. Preda, D. Cristea, C. Iorgulis, Gh. Negut, M. Parvan
• S4-3 Overview of Construction, Operations Planning and Commissioning of the OPAL Research Reactor
  G. Storr
• S4-4 LEU Experience on the Training Reactor VR-1 SPARROW
  K. Matejka, J. Rataj, L. Sklenka, R. Skoda
• S4-5 High Flux Reactor Petten - 6 Months after Conversion
  F. Wijtsma

Conversion Analysis

• S5-1 Calculation Studies to Substantiate Trial of Pilot Low-Enriched FAs in the WWR-K Reactor
  F. Arinkin, P. Chakrov, L. Chekushina, Sh. Gizatulin, K. Kadyrzhanov, S. Koltochnik, V. Nasonov, A. Taliev, Zh. Zhotabaev, Zh. Zhumadilova
• S5-2 Core Conversion Analyses for the Portuguese Research Reactor
  J. Matos, J. Stevens, E. Feldman, J. Stillman, F. Dunn, K. Kalimullah, J. Marques, N. Barradas, A. Ramos, A. Kling
• S5-3 Steady-State and Loss-of-Flow Transient Modeling for Tajoura Nuclear Research Reactor
  F. Bsebsu, P. Garner, N. Hanan
• S5-4 Analyses of the IRT, Sofia Initial LEU Core Performance
  T. Apostolov, S. Belousov, N. Hanan, J. Matos
• S5-5 Conversion of Australia's HIFAR Research Reactor to LEU Fuel
  G. Storr
• S8-1 Physics Design for in Hospital Neutron Irradiator with LEU Fuel
  K. Guo-tu, S. Zhi-yong, L. Zheng, S. Feng
• S8-2 Monte Carlo Calculations for Low-Enrichment of MNSR Fuel
  L. Yiguo, X. Pu
• S8-3 Criticality Calculations and Transient Analysis of the Nigeria MNSR (NIRR-1) for Conversion to LEU
  S. Jonah, J. Liaw, J. Matos, A. Olson
• S8-4 Progress in the Neutronic Core Conversion (HEU-LEU) Analysis of Ghana Research Reactor-1
  S. Anim-Sampong, B. Maakuu, E. Akaho, A. Andam, J. Liaw, J. Matos
• S13-1 Reactivity-Induced Transient Modeling for Tajoura Nuclear Research Reactor with HEU and LEU Fuel
  F. Bsebsu, P. Garner, N. Hanan
• S13-2 Recent Improvements to Steady-State Thermal-Hydraulic Analysis of Research Reactors in the RERTR Program at ANL
  A. Olson, Kalimullah, E. Feldman
• S13-3 Planning of Conversion at the Reactor WWR-SM by Low Enrichment U-235 on Less than 20%
  U. Salikhbaev, A. Dosimbaev, S. Baytelesov
• S16-1 WWR-SM Conversion to LEU IRT-4M Oxide Fuel
  N. Hanan, U. Salikhbaev, S. Baytelesov, A. Dosimbaev
• S16-2 Characteristics of the WWR-K Reactor Core with Low-Enriched Uranium Dioxide Fuel
  F. Arinkin, P. Chakrov, L. Chekushina, Sh. Gizatulin, K. Kadyrzhanov, E. Kartashev, S. Koltochnik, V. Lukishev, V. Nasonov, A. Taliev, Zh. Zhotabaev
• S16-3 Investigating the Potential of Monolithic UMo for the Conversion of FRM-II
  M. Englert, W. Liebert
• S16-4 Conceptual Neutronic Design of an Advanced HANARO Reactor Using the U3Si2 and U-Mo Fuel
  C. Seo, C. Lee, B. Lee, H. Chae

Fuel Development

• S6-1 Progress in the U.S. RERTR Fuel Development Program
  M. Meyer, R. Ambrosek, G. Chang, C. Clark, M. FInlay, G. Hofman, D. Keiser, D. Meyer, G. Moore, K. Moore, J. Snelgrove, D. Wachs, T. Wiencek, J. Wight, J. Williams
• S6-2 Current Status of the Development of High Density LEU Fuel for Russian Research Reactors
  A. Vatulin, I. Dobrikova, V.Suprun, E. Kartashev, V. Lukichev, V. Troyanov, A. Enin, P. Shornikov
• S6-3 Development of Dispersed UMo fuel : An Oxide Layer as a Protective Barrier of the UMo Particles
  S. Dubois, F. Mazaudier, H. Palancher, P. Martin, C. Sabathier, M. Ripert, P. Lemoine, C. Jarousse, M. Grasse, N. Wieschalla, W. Petry
• S6-4 Advanced Development in U-Mo Dispersed and Monolithic Fuels
  E. Pasqualini
• S9-1 Update on Monolithic Fuel Fabrication Methods
  C. Clark, J. Jue, G. Moore, N. Hallinan, B. Park, D. Burkes
• S9-2 Fuel Manufacture in South Africa: The Road to Conversion
  R. Jamie, A. Kocher
• S9-3 Design and Status of RERTR Irradiation Tests in the Advanced Test Reactor
  D. Wachs, R. Ambrosek, G. Chang, M. Meyer
• S9-4 Update on Uranium-Molybdenum Fuel Foil Fabrication Development at the Y-12 National Security Complex
  R. Dunavant, A. DeMint, J. Holt
• S9-5 Preparation of Life-Time Test of the Full-Scale IRT-Type Fuel Assembly in the MIR Reactor
  A. Vatulin, I. Dobrikova, V. Suprun, E. Kartashev, V. Lukichev, V. Troyanov, A. Enin
• S9-6 Manufacturing Results of Monolithic UMo Full Size Prototype Plates
  C. Jarousse, P. Lemoine, P. Boulcourt, W. Petry, A. Rohrmoser
• S11-1 Post Irradiation Examination of Monolithic Mini Fuel Plates From RERTR-6
  M. Finlay, D. Wachs, G. Hofman
• S11-2 Results of Low-Enriched U-Mo Miniplates from RERTR-6 and -7A Irradiation
  G. Hofman, Y. Kim, H. Ryu, M. Finlay
• S11-3 Results of PIE Pin-type LEU U-Mo Fuel Elements Irradiated in the MIR Reactor
  A. Izhutov, V. Alexandrov, A. Novosyolov, V. Starkov, G. Shevlyakov, V. Shishin, V. Yakovlev, A. Vatulin, I. Dobrikova, V. Suprun, Y. Trifonov
• S11-4 U-Mo Foil/Cladding Interactions in Monolithic RERTR Fuel Plates
  D. Keiser, Jr., J. Jue, C. Clark, J. Wight
• S11-5 Interdiffusion Behaviors of U-Mo-Zr/Al-Si
  J. Park, H. Ryu, S. Oh, D. Lee, C. Kim, Y. Kim, G. Hofman
• S15-1 Interaction Layer Growth Correlations for (U-Mo)/Al and Si-added (U-Mo)/Al Dispersion Fuels
  Y. Kim, H. Ryu, G. Hofman, S. Hayes, M. Finlay, D. Wachs, G. Chang
• S15-2 Simulation with PLACA/DPLACA of Monolithic and Dispersed Fuel Plates
  A. Soba, A. Denis
• S15-3 Diffraction Measurements on Heavy Ion Bombarded U-Mo/Al Dispersion Fuel Using Synchrotron Radiation
  N. Wieschalla, W. Petry, T. Wroblewski, C. Bogenberger, R. Jungwirth, W. Schmid, A. Rohrmoser
• S15-4 Characterization of the Interaction Products in U-Mo/Al Dispersion Fuel from In-pile and Out-of-pile Tests
  H. Ryu, Y. Kim, G. Hofman and D. Keiser

U.S. Reactor Conversion

• S12-1 U. S. University Reactor Conversion Program
  D. Meyer and E. Woolstenhulme
• S12-2 Analyses for the Conversion of the Purdue University Reactor from HEU to LEU Fuel
  J. Jenkins, J. Anglin, C. Glass, J. Matos, J. Stillman
• S12-3 Current Status of the Missouri University Research Reactor HEU to LEU Conversion Feasibility Study
  L. Foyto, J. C. McKibben, K. Kutikkad
• S12-4 Core Design and Analysis for the MIT Reactor Using Monolithic U-Mo LEU Fuel
  T. Newton
• S12-5 Design Study for a Low Enriched Uranium Core of the High Flux Isotope Reactor
  R. Primm, R. Ellis, J. Gehin, D. Moses
• S12-6 Advanced Test Reactor LEU Fuel Conversion Feasibility Study Annual 2006 Report
  G. Chang and R. Ambrosek

Mo-99 Production

• S10-1 Progress in the IAEA Coordinated Research Project on Molybdenum-99 Production Using LEU or Neutron Activation
  I. Goldman, N. Ramamoorthy, P. Adelfang
• S10-2 Production of fission 99Mo by LEU foil irradiation. Status of the Chilean Project.
  J. Medel, J. Marín, R. Schrader
• S10-3 Progress in Technology Development for Conversion of 99Mo Production from HEU to LEU Targets – Development of New Separation Schemes, and New Processing Equipment
  A. Bakel, D. Stepinski, A. Guelis, A. Hebden, A. Leyva, L. Hafenrichter, P. Gentner, and G. Vandegrift
• S10-4 Progress in Technology Development for 99Mo Isotope Production
  C. Toma, C. Iorgulis, P. Busuioc, Gh. Negut, St. Covaci
• S10-5 Feasibility Study – Production of Fission Product Mo-99 Using the LEU-Modified Cintichem Process, University of Missouri Research Reactor
  C. Allen, R. Butler, W. Miller

Transportation

• S14-1 Update on NAC's Transportation Projects: Recent and Prospective Spent Nuclear Fuel Shipments
  C. Anne, J. Adam
• S14-2 The Experience of Shipping Spent Nuclear Fuel From Uzbekistan to the Russian Federations
  B. Yuldashev, U. Salikhbaev, I. Bolshinsky, J. Thomas
• S14-3 Ten Years Experience Shipment of Spent Fuel From GKSS to the US under the FRRSNF Acceptance Program
  A. Drawe, H. Hager, P. Schreiner
• S14-4 Casks for Irradiated Fuel from Research Reactors
  M. Mandla, H. Tschiesche
• S14-5 TN International Transport Solution: Supporting Non-proliferation Initiative
  D. Ohayon, L. Mariette, V. Garcia

POSTER SESSION

• S7-1  Update on U-Mo Fuel Processing and Characterization
  G. Moore, J. Jue, C.Clark, D. Burkes
• S7-2  Analyses of Flow Excursion Experiments Relevant to Research Reactors: Revisited
  A. Olson
• S7-3  Results for the Recent Activities of Reduced Enrichment Program for Research Reactors in Chile
  M. Barrera, J. Lisboa, J. Marin, L. Olivares, K. Bakker, F. Wijtsma
• S7-4  Development of Radiographic Examination Method of SAFARI-1 LEU Fuel Plates
  J. de Villiers
• S7-5  Thermodynamic and Kinetic Features of the Oxidation Treatment of U7Mo Particles
  F. Mazaudier, C. Proye, J. Miragaya, S. Dubois, P. Lemoine, C. Jarousse, M. Grasse
• S7-6  A Method of Determining a Start of Porosity and Defect Formation in the Fuel Elements with U-Mo Fuel
  O. Golosov, M. Lyutikova, E. Kartashev, V. Lukichev
• S7-7  Modeling the Integrated Performance of Dispersion and Monolithic U-Mo Based Fuels
  D. Wachs, D. Burkes, S. Hayes, K. Moore, G. Miller, G. Hofman, Y. Kim
• S7-8  Mixed Fuel Versus Low Enriched Fuel in the Syrian MNSR
  M. Albarhoum
• S7-9  Production of Iodine-131 from Low Enriched Uranium Targets
  P. Cristini, D. Cestau, R. Bavaro, M. Bronca, R. Centurión, A. Novello, J. Cestau, E. Carranza