Abstracts and Available Papers Presented at the
2005 International RERTR Meeting

The 27^th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) was held in Boston, USA on November 6-10, 2005. The available abstracts and papers that were presented at this meeting are provided below.

Opening Remarks

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

Reduced Enrichment and Repatriation Programs

• S2-1 The RERTR Program: Status and Current Plans
  P. Staples
• S2-2 Latest IAEA Activities Related to Research Reactor Fuel Conversion and Spent Fuel Return Programs
  P. Adelfang
• S2-3 Progress on RERTR Activities in Argentina
  H. Taboada, S. Balart, N. Boero, O. Calzetta, A. Gauna, J. Hermida, A. Manzini, and E. Pasqualini
• S2-4 Status of Reduced Enrichment Program for Research Reactors in Japan
  Y. Nakagome, H. Unesaki, and H. Sagawa
• S2-5 South Africa and the SAFARI-1 Scenario: On The Road to Conversion - from HEU to LEU
  C. Piani
• S2-6 The United States Foreign Research Reactor Spent Nuclear Fuel Acceptance Program: Program Continuation and Current Initiatives
  C. Messick and J. Taylor
• S2-7 RRRFR Program
  I. Bolshinsky

Related Programs

• S3-1 Filling the Gaps
  P. Khalsa
• S3-2 Disposition Options for GAP Materials
  J. Dewes
• S3-3 Global Research Reactor Security Program
  P. Robinson

Reactor Conversion Experience

• S4-1 Safety Re-evaluation and Relicensing of the HFR Petten
  F. Wijtsma
• S4-2 Sparrow Flies Lower
  R. Skoda
• S4-3 Criticality Calculations and Transient Analyses for the VR-1 Reactor with IRT-4M LEU Fuel Assemblies
  J. Rataj
• S4-4 The First Critical Experiment with a LEU Russian Fuel IRT-4M at the Training Reactor VR-1
  L. Sklenka and K. Matejka

Fuel Development Programs

• S5-1 Status and Progress of the U.S. RERTR Fuel Development Program
  M. Meyer
• S5-2 Main Results of the Development of LEU Fuel for Russian Research Reactors
  A. Vatulin, I. Dobrikova, A. Morozov, and V. Suprun
• S5-3 Staus of the French CEA Program for the Development and the Qualification of High Density Fuel for the JHR Project
  P. Lemoine

U-Mo Fuel Development and Testing

• S6-1 Irradiation Testing of High Density U-Mo Fuels in the ATR
  D. Wachs, G. Chang, R. Ambrosek, and M. Meyer
• S6-2 Results of Post Irradiation Examinations of Pin Type Low Enriched U-Mo Mini Fuel Elements
  A. Izhutov, A. Novosyolov, V. Shishin, V. Alexandrov, N. Gataulin, V. Starkov, G. Shevlyakov, V. Yakovlev, and A. Sheldyakov and I. Dobrikova, A. Vatulin, G. Kulakov, and A. Morozov
• S6-3 Progress of KOMO-3 Irradiation Test for Various U-Mo Dispersion and Monolithic Fuel to Overcome Interaction Problem in U-Mo/Al Dispersion Fuel
  C. Kim, K. Kim, J. Park, H. Ryu, Y. Lee, D. Lee, S. Oh, H. Chae, C. Seo, and C. Lee
• S6-4 Test of Pin Fuel in WWW-M Reactor
  A. Zakharov, G. Kirsanov, K. Konoplev, and A. Morozov
• S13-1 Observations of the Nucleation and Evolution of Porosity in U-Mo Fuels
  G. Hofman and M. Finlay
• S13-2 Out-of-Pile Diffusion Studies Between U-7wt%Mo and Al-Si Alloys
  M. Mirandou, S. Aricó, L. Gribaudo, and S. Balart
• S13-3 Phase Stability and Diffusion Characteristics of U-Mo-X (X=Si, Al, Zr or Ti) Alloys
  J. Park, H. Ryu, G. Lee, H. Kim Y. Lee, C. Kim, and Y. Kim and G. Hofman
• S13-4 Study of UMo/Al Interaction Layer by XRD and XAS with Micro-Focused X-Ray Beam
  H. Palancher, P. Martin, M. Ripert, S. Dubois, and C. Valot, and C. Proyne and F. Mazaudier
• S14-1 Heavy Ion Irradiation of U-Mo/Al Dispersion Fuel
  N. Wieschalla, A. Bergmaier, P. Bonib, K. Boning, G. Dollinger, R. Grossmann, W. Petry, A. Rohrmoser, and J. Schneider
• S14-2 Effects of Additives in the Al Interdiffusion Behavior in UMo Based Fuels
  J. Garces, G. Bozzolo, G. Hofman, and J. Rest
• S14-3 Thermodynamic and Metallurgical Considerations to Stabilizing the Interaction Layers of U-Mo/Al Dispersion Fuel
  Y. Kim
• S14-4 Main Interactions in the Formation Energy of BCC Gamma (U,Mo) Disordered Phase
  P. Alonso and G. Rubiolo

U.S. Reactor Conversion

• S7-1  Domestic Reactor Conversions Program Overview and Status
  D. Meyer and J. Wade
• S7-2  Florida
  B. Dionne
• S7-3  HEU to LEU Conversion Analysis of the Texas A&M TRIGA Reactor
  J. Bolin, W. Whittemore, C. Ellis, H. Yi, A. Veca
• S7-4  Advanced Test Reactor LEU Fuel Conversion Feasibility Study
  G. Chang and R. Ambrosek
• S7-5  Overview of High Flux Isotope Reactor Design Bases Relevant to Possible Conversion to Low-enriched Uranium
  R. Primm III, D. Moses, J. Gehin, R. Ellis, and J. Binder

Mo-99 Production

• S8-1  Facts and Myths Concerning ⁹⁹Mo Production with HEU and LEU Targets
  G. Vandegrift
• S8-2  The Radiopharmaceutical Industry's Effort to Migrate Towards Mo-99 Production Utilizing LEU
  R. Brown
• S8-3  Radionuclide Purity of Fission Mo-99 Produced from LEU and HEU: A Comparative Study
  A. Durán
• S8-4  Weaker U.S. Export Controls on Bomb-Grade Uranium: Causes, Consequences, Prospects
  A. Kuperman
• S8-5  Progress in Technology Development for Conversion of ⁹⁹Mo Production - Batan's (Indonesia) Conversion program and Development of Inorganic Sorbents for ⁹⁹Mo Production
  A. Bakel, D. Stepinski, G. Vandegrift, A. Leyva, A. Gelis, A. Bond, and H. Mayes
• S8-6  The IAEA Coordinated Research Project on Molybdenum-99 Production Using LEU or Neutron Activation
  I. Goldman and P. Adelfang

Program Extensions

• S9-1 The RERTR Current Scope of Work for Reactor Conversions
  C. Landers
• S9-2 About the Enrichment Limit for Research Reactor Conversion: Why 20%?
  A. Glaser
• S9-3 Future Needs for HEU-fueled Critical Assemblies
  F. Von Hippel
• S9-4 Assessment of Feasibility of Converting Russian Icebreaker KLT-40 Reactors from HEU to LEU Fuel
  A. Dmitriev, A. Diakov, and A. Shuvaev

REACTOR CONVERSION ANALYSIS

• S10-1 The Feasibility Study of LEU Fuel for Miniature Neutron Source Reactor
  L. Yiguo and X. Pu
• S10-2 Feasibility Study of Potential LEU Fuels for a Generic MNSR Reactor
  J. Matos and R. Lell
• S10-3 The Use of UAlx-Al Reduced Enrichment Fuel in a Well Reflected MNSR
  M. Albarhoum
• S10-4 Current Status of the Nigeria MNSR (NIRR-1) and Feasibility for Conversion to LEU
  S. Jonah and G. Balogun
• S10-5 Monte Carlo Simulation of Irradiation Channels of the HEU-fueled GHARR-1 Facility
  S. Anim-Sampong, B. Maakuu, E. Akaho, and B. Nyarko
• S10-6 Enhancement of Pakistan Research Reactor-2 Reactivity by Beryllium Shim Plate Addition and Comparison of Pre-shimming and Post-shimming Reactor Operation Data
  M. Abdullah
• S11-1 Comparative Analysis for Loading LEU Instead of HEU Fuel Assemblies in the Dalat Nuclear Research Reactor
  V. Le, T. Huynh, B. Luong, and V. Pham and J. Liaw and J. Matos
• S11-2 Feasibility Analysis for Conversion of the WWR-K Reactor Using an Eight-Tube Uranium Dioxide Fuel Assembly
  F. Arinkin, P. Chakrov, L. Chekushina, I. Dobrikova, Sh. Gizatulin, K. Kadyrzhanov, S. Koltochnik, V. Nasonov, A. Taliev, A. Vatulin, Zh. Zhotabaev, and N. Hanan
• S11-3 Completion of the Safety Analysis for the WWR-M Reactor in Ukraine to Allow Operation Using LEU Fuel
  Y. Mahlers and A. Dyakov
• S16-1 Core Conversion of the Portuguese Research Reactor: An Operator's Perspective J. Marques et al.
• S16-2 Neutronic Parameters of Tajoura Research Reactor Fueled with HEU and LEU
  O. Abulgasem, F. Abuatweirat, and A. Ajaj
• S16-3 Progress in Conversion from HEU to LEU Fuel at IRT-200, Sofia
  T. Apostolov, S. Belousov, P. Egorenkov, and J. Deen, N. Hanan, and J. Matos
• S16-4 Comparative Study of the WWR-K Reactor Using Low Enriched U-Mo Fuel Pin- and Tube-Type Assemblies
  F. Arinkin, P. Chakrov, L. Chekushina, I. Dobrikova, Sh. Gizatulin, K. Kadyrzhanov, S. Koltochnik. V. Nasonov, A. Taliev, A. Vatulin, Zh. Zhotabaev

Fuel Fabrication

• S15-1 Update on Monolithic Fuel Fabrication Development
  C. Clark, J. Wight, G. Knighton, G, Moore, and J. Jue
• S15-2 Monolithic U-Mo Full Size Prototype Plates Manufacturing Development
  C. Jarousse, P. Lemoine, W. Petry, and A. Rohrmoser
• S15-3 Dispersed (Coated Particles) and Monolithic (Zircalloy-4 Cladding) UMo Miniplates
  E. Pasqualini
• S15-4 Recent Developments of Magnesium Matrix Fuel Plates
  T. Wiencek
• S15-5 BWXT Commercialization Activities for GTRI LEU U-Mo Fuels
  M. Nilles, G. Gale, and R. Kunz

Spent Fuel Management

• S17-1 Successful Removal of More Than 200 Spent HEU Fuel Assemblies from the High Flux Reactor at Petten
  C. Anne, F. Wijtsma, F. de Smedt, and A. Gevers
• S17-2 Options for the Management of Spent Fuel from Research Reactors in Latin American Countries - A Report from the IAEA Technical Cooperation Regional Project RLA/4/018
  A. Bevilacqua, O. Novara, A. Soares, J. Klein, R. Mazon, I. Llamas, and P. Adelfang
• CS17-3  Containment Evaluation of Breached AL-SNF for Cask Transport
  D. Vinson, R. Sindelar, and N. Iyer

POSTER SESSION

• S12-1 RERTR Program Cooperation with the IAEA Technical Cooperation Program
  D. Chong
• S12-2 Lessons from the Atoms-for-Peace Research Reactor Fuels Program, 1955-1965
  S. Zinkle, D. Moses, T. Huxford, and J. Binder
• S12-3 Under Irradiation Qualification of a Chilean Test Fuel
  J. Marin, J. Lisboa, and L. Olivares
• S12-4 Effect of Reaction Phase Growth on the Irradiation Performance of Rod-type U-Mo/Al Dispersion Fuel
  H.J. Ryu, J. Park, H. Chae, C. Kim, Y. Kim, and G. Hofman
• S12-5 Analysis of Factors Affecting the Formation of Porosity and Bulges in U-Mo Fuel
  A. Savchenko, A. Vatulin, I. Dobrikova, G. Kulakov, S. Ershov, Y. Konovalov
• S12-6 First Principles Calculations of Lattice Parameter and Elastic Constant of BCC Gamma(U, Mo) Disordered Phase
  P. Gargano, P. Alonso, H. Mosca, J. Rios, M. Albuixech, and G. Rubiolo
• S12-7 Monolithic Fuel Plates Diffusion Bonded by Electro-consolidation
  I. Prokofiev
• S12-8 Calculation Studies on Conversion to Low Enriched Fuel of Research Reactor in Libya
  V. Lukichev, V. Aden, E. Kartashev, …,S. Sokolov, and V. Nikitin
• S12-9 Using Low-Enriched Uranium in the VNIIIEF Pulsed Reactors
  A. Dubinin
• S12-10 Study on Usage of Low Enriched Uranium Russian Type Fuel Elements for Design of an Experimental ADS Research Reactor
  M. Pesic
• S12-11 Progress Achieved for the Full Conversion - from HEU to LEU - of the TRIGA 14 MV Research Reactor Core at Pitesti, Romania
  A. Atger, L. Biro, I. Bolshinsky, M. Ciocanescu, and J. Falgoux