2007 International RERTR Meeting
Abstracts and Available Papers Presented at the Meeting
The 29th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) was held September 23-27, 2007 at the Diplomat Hotel in Prague, Czech Republic. The available abstracts and papers that were presented at this meeting are provided below.
Welcome to Czech Republic
- Welcome
Ms. D. Drabova, State Office of Nuclear Safety
Professor L. Musilek, Vice-Rector of CTU
Opening Programmatic Remarks
- S1-1 Opening Remarks - United States
N. Miller - S1-2 Opening Remarks - IAEA
H. Forsström - S1-3 Overview of NNSA Non-Proliferation
Programs
K. Baker - S1-4 Global Initiative to Combat Nuclear
Terrrorism
A. Grant
HEU Minimization and Conversion Programs
- S2-1 GTRI Program Overview
A. Bieniawski - S2-2 International Atomic Energy Agency
Support of Research Reactor Highly Enriched Uranium to
Low Enriched Uranium Fuel Conversion Projects
E. Bradley, P. Adelfang, I. Goldman - S2-3 Measuring Progress on HEU Minimization
- The Need for Acceleration and Addressing "Out-of
Scope" Activities
O. Reistadt, S. Hustveit, M. Mærli - S2-4 Developing HEU Guidelines
C. Chuen - S2-5 Progress on RERTR Activities in
Argentina
S. Balart, O. Calzetta, P. Cristini, J. Garcés, A.G. Gonzalez, J.D. Hermida, M. Mirandou, O. Novara, H. Taboada - S2-6 SAFARI-1: Achieving Conversion to LEU
- A Local Challenge
C. Piani - S2-7 What is New with GTRI Since Cape Town
J. Edlow
Conversion Experience
- S3-1 Status of Reduced Enrichment Program
for Research Reactors in Japan
H. Unesaki, H. Sagawa - S3-2 Core Conversion of the Portuguese
Research Reactor to LEU Fuel
J. Marques - S3-3 Progress Report on the Conversion of
the Purdue University Reactor, PUR-1, from HEU to LEU
J. Jenkins, E. Merritt, B. Revis - S3-4 HFR Towards Manufacturing Excellence
E. de Widt, F. Wijtsma
Conversion Analysis
- S5-1 Impact of the HEU/LEU Conversion on
Experimental Facilities
M. Marek, J. Kysela, J. Ernest, S. Flibor, V. Broz - S5-2 Preliminary Study on New Configuration
with LEU Fuel Assemblies for the Dalat Nuclear
Research Reactor
V. Pham, V. Le, T. Huynh, B. Luong, K. Nguyen - S5-3
Neutronics and Steady-State Thermal
Hydraulics Analysis for the HEU, Mixed HEULEU and the
First Full LEU Cores of WWRSM Reactor at INP AS Ruz
S. Baytelesov, A. Dosimbaev, F. Kungurov, U. Salikhbaev - S5-4 Performance Gain with Low-Enriched
Fuel and Optimized Use of Neutrons
A. Glaser - S10-1 MNSR Flux Performance and Core
Lifetime Analysis with HEU and LEU Fuels
J. R. Liaw, J. E. Matos - S10-2 The Study of Physics and
Safety Characteristics for In-Hospital Neutron
Irradiator (IHNI)
K. Guotu, S. Ziyong, L. Zheng, S. Feng, L. Tiancai - S10-3
The Physics
Experimental Study for In-hospital Neutron Irradiator
L. Yiguo, X. Pu, Z. Shuyun, Z. Yongbao, L. Zheng, Z. Wuqing, S. Yongqian, G. Jijin, Z. Yongmao - S10-4
Progress in the Conversion Activity
of the Syrian MNSR
M. Albarhoum - S14-1
Results of Transient/Accident
Analysis for the HEU, First Mixed HEU-LEU, and for the
First Full LEU Cores of the WWR-SM Reactor at INP AS
Ruz
S. Baytelesov, A. Dosimbaev, F. Kungurov, U. Salikhbaev - S14-2 Investigation of Approximations in
Thermal- Hydraulic Modeling of Core Conversions
P.L. Garner, N. A. Hanan - S14-3
Comparative Assessment of Nuclear
Criticality and Neutronic Performance Indicators of
12.1% Enriched LEU UO2 Fuels for Conversion
of the Ghana MNSR Facility
S. Anim-Sampong, J. Liaw, J. Matos, B. Maakuu, G. Banini, A. Andam, E. Amponsah-Amoako, S. Attakorah, I. Lawson, R. Sogbadji, G. Quao - S14-4 Calculations of MARIA Reactor Using
REBUS and MCNP Codes
K.J. Andrzejewski, T.A. Kulikowska, Z.E. Marcinkowska, W. Mieleszczenko, K.M. Pytel, N. Hanan - S14-5 Fuel Management for Research Reactors
in the Czech Republic
J. Kysela, J. Rychecky, V. Rypar, K. Matejka, L. Sklenka - S16-1
Fundamental Approach to TRIGA Steady
State Thermal-Hydraulic CHF Analysis
E. Feldman - S16-2 MNSR Transient Analyses and
ThermalHydraulic Safety Margins for HEU and LEU Cores
Using PARET
A. Olson, S. Jonah - S16-3 Consequences of Potential Radiation
Accident in the WWR-K Reactor at Life Test of LTA with
Low-Enriched Fuel
F. Arinkin, P. Chakrov, L. Chekushina, Sh. Gizatulin, S. Koltochnik, N. Romanova, A. Tuleushev, A. Shaimerdenov - S16-4
Optimization from Core to Experiment
- Using Monte Carlo Computer Codes for the Conversion
of High Flux Neutron Sources
M. Englert
Fuel Development
- S4-1 Status and Progress in the U.S. RERTR
Fuel Development Program
D. Wachs - S4-2 Current Status of the Development of
High Density LEU Fuel for Russian Research Reactors
A. Vatulin, I. Dobrikova, V. Suprun, Y. Trifonov, E. Kartashev, V. Lukichev - S4-3 Nuclear Fuel Development Based on UMo
Alloys Under Irradiation Evaluation of LEU U3Si2 - 4.8 gU/cm3 Test Fuel
L. Olivares, J. Marin, M. Barrera, G. Torres and J. Lisboa - S4-4 Foil Fabrication and Barrier Layer
Application for Monolithic Fuels
G. Moore, C. Clark, J. Jue, W. D. Swank, D. Haggard, M. Chapple, D. Burkes - S4-5 The Technique and Preliminary Results
of LEU U-Mo Full Size IRT Type Fuel Elements in the
MIR Reactor
A. Izhutov, V. Starkov, V. Pimenov, V. Fedoseev, I. Dobrikova, A. Vatulin, V. Suprun, Y. Kartashov, V. Lukichev - S8-1 Development of Technology of High
Density LEU Dispersion Fuel Fabrication
T. Wiencek, T. Totev - S8-2 Update on Friction Bonding of
Monolithic U- Mo Fuel Plates
D. Burkes, N. P. Hallinan, J. Wight, M. Chapple, C. Clark - S8-3 Development of Monolithic Nuclear
Fuels for RERTR by Hot Isostatic Pressing
J. Jue, B. Park, M. Chapple, G. Moore, D. Keiser - S8-4 Update on Uranium-Molybdenum
Fuel Foil
Fabrication Development at the Y-12 National Security
Complex in 2007
A. DeMint, J. Gooch, R. Dunavant, T. Andes - S8-5 Powder Formation of γ-UMo Alloys via
Hydration - Dehydration
F. de Oliveira, M. Durazzo, E. de Carvalho, A. Saliba-Silva, H. Riella - S8-6 Considerations in the Development of a
Process to Manufacture Low-enriched Uranium Foil Fuel
for the High Flux Isotope Reactor
J. Sease, R. T. Primm, J. Miller - S13-1 Observations Derived from the
Characterization of Monolithic Fuel Plates Irradiated
as Part of the RERTR6 Experiment
D. Keiser, A. Robinson, M. Finlay - S13-2
Transmission Electron Microscopy
Investigation of Irradiated U-7 wt% Mo Dispersion Fuel
S. Van den Berghe, W. Van Renterghem, A. Leenaers - S13-3
Post Irradiation Analysis and
Performance Modeling of Dispersion and Monolithic U-Mo
Fuels
Y. S. Kim, G. Hofman, P. Medvedev, G. Shevlyakov, A.B. Robinson, H.J. Ryu - S13-4
Improvement in the Structure
Identification of the Phases in the Interaction Layers
UMo/ Al or Al-Si Employing High Intensity Xray
Diffraction
M. Mirandou, S. Balart, C. Varela, S. Aricó, A. Fortis - S15-1 Post Irradiation Analysis of
RERTR-7A, 7B, and RERTR-8 Tests
G.L. Hofman, Y. S. Kim, A.B. Robinson, G.V. Shevlyakov - S15-2 Production and Characterization of
Atomized U-Mo Powder by the Rotating Electrode Process
C. Clark, B. Muntifering, J. Jue, M. Chapple - S15-3 Phase Stability of U-Mo Ti Alloys and
Interdiffusion Behaviours of U-Mo-Ti/Al-Si
J. M. Park, H. Ryu, J. S. Park, S. Oh, C. Kim, Y. S. Kim, G. Hofman - S15-4
Results of PIE of Experimental
(U-Mo)- Based LEU Disperse Fuel Compositions
A. Vatulin, I. Dobrikova, V. Suprun, Y. Petrov, Y. Trifonov, V. Alexandrov, A. Izhutov, A. A. Novoselov, V. Starkov, V. Shishin, V. Yakovlev - S17-1
Small Angle Neutron Scattering by
U-9% Mo/Al Dispersion Fuel Irradiated to High
Burn-ups
O.A. Golosov, V.B. Semerikov, S.G. Bogdanov, M.S. Lyutikova - S17-2 Simulation with PLACA/DPLACE of
Thermal and Mechanical Phenomena in Monolithic and
Dispersed Fuel Plates
A. Soba, A. Denis - S17-3
MTR Plates Modeling with MAIA
V. Marelle, S. Dubois, M. Ripert, J. Noirot
U.S. Reactor Conversion
- S12-1 U. S. University Reactor Conversion
Program
D. Meyer and E. Woolstenhulme - S12-2 ATR LEU Fuel and Burnable Absorber
Neutronics Performance Optimization by Fuel Plate
Thickness Variation
G. Chang - S12-3
Progress Made on the University of
Missouri Research Reactor HEU to LEU Fuel Conversion
Feasibility Study
J. C. McKibben, K. Kutikkad, L. Foyto - S12-4 Reactor Core Design and Modeling of
the MIT Research Reactor for Conversion to LEU
T. Newton, A. Olson, J. Stillman - S12-5 Validation of the MULCH-II Code for
Thermal- Hydraulic Safety Analysis of the MIT Reseach
Reactor Conversion to LEU
Y-C. Ko, L-W. Hu, A. Olson, F. Dunn
Mo-99 Production
- S6-1
Indonesia's Current Status for
Conversion of Mo-99 production to LEU Fission
B. Briyatmoko, Boybul, Guswardani, Suhardyo, Purwanta - S6-2
Overview of 2007 ANL Progress for
Conversion of HEU-Based Mo-99 production as part of
the U.S. Global Threat Reduction Conversion Program
G. Vandegrift, A. Bakel, A. Guelis, L. Hafenrichter, A. Hebden, J. Jerden, A. Leyva, K. Quigley, D. Stepinski - S6-3 Progress and
Status of the IAEA Coordinated Research Project:
Production of Mo-99 Using LEU Fission or Neutron Activation
I. Goldman, N. Ramamoorthy, P. Adelfang - S6-4 HEU and LEU Comparison in the
Production of Molybdenum-99
D. Cestau, P. Cristini, A. Novello, M. Bronca, R. Centurión, R. Bavaro, J. Cestau, E. Carranza - S9-1
Status Report on Technical Progress for LEU-based
99Mo Production at Argonne National Laboratory
Allen Bakel, Artem Guelis, Lohman Hafenrichter, Andrew Hebden, James Jerden, Argentina Leyva, Kevin Quigley, Dominique Stepinski, and George F. Vandegrift - S9-2 Feasibility Study Part 1 - Thermal
Hydraulic Analysis of LEU Target for Mo-99 Production
in Tajoura Reactor
F. Bsebsu, F. Abotweirat, S. Elwaer - S9-3 Feasibility Development Program LEU-Foil
Plate Type Target for the Production of Mo- 99
C. Allen, R. Butler, C. Jarousse, JL. Falgoux - S9-4 Progress in Chile in the Development
of the Fission Mo-99 Production Using CINTICHEM
R. Schraeder, J. Klein, J. Medel, J. Mar ín, N. Salazar, C. Albornoz, M. Chandia, X. Errazu, R. Becerra - S9-5
Tc-99m Generators for Clinical Use
Based on Zirconium Molybdate Gel and (n,γ) Produced
Mo- 99: Indian Experience in the Development and
Deployment of Indigenous Technology and Processing
Facilities
P. Saraswathy, A. Dey, S. Sarkar, C. Kothalkar, P. Naskar, G. Arjun, S. Arora, A. Kohli, V. Meera, V. Venugopal, N. Ramamoorthy
Transportation and Fuel Disposition
- S7-1 Present Experience of the NRI REZ with
Preparation of Spent Nuclear Fuel Shipment to Russian Federation
F. Svitak, V. Broz, M. Hrehor, M. Marek, P. Novosad, J. Podlaha, J. Rychecky - S7-2 Update on Y-12 National Security
Complex Activities to Recover Enriched Uranium in 2007
B. Eddy, T. Andes, R. Dunavant - S7-3 GTRI's Russian Fuel Return Program
Progress
K. Cummins, I. Bolshinsky - S7-4 The United States Foreign Research
Reactor (FRR) Spent Nuclear Fuel (SNF) Acceptance
Program: 2007 Update
C. Messick, J. Taylor
POSTER SESSION
- S11-1 Generic Methodology for
Assessment of Reasearch Reactor Fuel Integrity
T. Totev - S11-2 Identification
of Phases in the Interaction Layer between U-Mo-Zr/Al and U-Mo-Zr/Al-Si
C. K. Varela, S. Aricó, M. Mirandou, S. Balart, L. Gribaudo - S11-3 Vinca Institute Safety and
Licensing Actions for Carbon Steel Structure Removal
from RA Research Reactor SNF Pool
M. Pešić, O. Šotić, S. Pavlović, V. Ljubenov, A. Nikolić - S11-4 MNSR
Transient Analyses and Thermal Hydraulic Safety
Margins for HEU and LEU Cores Using the RELAP5-3D Code
F. Dunn, J. Thomas, J. Liaw, J. Matos - S11-5 Microstructure of 50 Year Old SCK●CEN BR1 Research Reactor Fuel
A. Leenaers, S. Van den Berghe - S11-6
Technical Assumption for Mo-99
Production in the MARIA Reactor
J. Jaroszewicz, K. Pytel, L. Dąbkowski, G. Krzysztoszek - S11-7 Thermal-Hydraulic Calculations
for the Conversion to LEU of a Research Reactor Core
D. Grigoriadis, M. Varvayannim, N. Catsaros, E. Stakakis - S11-8 Current Status of U3Si2
Fuel Elements Fabrication in Brazil
M. Durazzo, A. Silva, J. de Souza, E. de Carvalho, H. Riella - S11-9 Neutronic Calculations for the
Conversion to LEU of a Research Reactor Core
M. Varvayanni, D. Grigoriadis, N. Catsaros, E. Stakakis - S11-10 Conversion: Experiences from
the Texas A&M University Reactor Conversion
J. Creasy - S11-11 Texas A&M HEU to LEU Conversion
Fabrication and Operational Performance
A. Veca, K. Mushinski - S11-12 Conversion of Research and
Test Reactors: Past Performance, Future Plans
N. Butler - S11-13 Determination
of Neutron Flux Density Distribution in the Core with LEU Fuel IRT-4M
at the Training Reactor VR-1
O. Huml - S11-14 Measurement of Gamma Field
Parameters in Core with LEU Fuel IRT-4M Using TL
Detectors
T. Bily - S11-15 The First Critical
Experiment with a LEU Russian Fuel IRT-4M at the
Training Reactor VR-1
J. Frybort - S11-16 The Determination of Neutron
Energy Spectrum in Core C1 of Reactor VR-1 Sparrow
M. Vins - S11-17 Comparison of Traditional
Nondestructive Analysis of RERTR Fuel Plates with
Digital Radiographic Techniques
T. Davidsmeier, R. Koehl, R. Lanham, E. O'Hare, T. Wiencek - S11-18 Thermal Hydraulic Analysis for
the Oregon State TRIGA Reactor Using RELAP5-3D
W. Marcum, B. Woods, M. Hartman