RERTR-2022 International Meeting
Vienna, Austria — October 2-5, 2022
Download the RERTR-2022 Technical Program by clicking on the image above.
Available Presentations
Presentations from the RERTR-2022 International Meeting on Reduced Enrichment for Research and Test Reactors are provided below.
DISCLAIMER
This report was prepared as an account of work sponsored by an agency of the United States
Government. Neither the United States Government nor any agency thereof, nor The University of
Chicago, nor any of their employees or officers, makes any warranty, express or implied, or assumes
any legal liability or responsibility for the accuracy, completeness, or usefulness of any information,
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recommendation, or favoring by the United States Government or any agency thereof. The views
and opinions of document authors expressed herein do not necessarily state or reflect those of
the United States Government or any agency thereof, Argonne National Laboratory, or The University
of Chicago.
| # | Title | Presenter | Affiliation | Topic |
|---|---|---|---|---|
| Welcome to the IAEA and RERTR-2022 International Meeting: A World of Progress and Reopening | Amb. L. Holgate DDG M. Chudakov V. Gnyrya J. Chamberlin |
UNVIE/US IAEA NNC/Kazakhstan NNSA/US |
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| S1-P1 | IAEA Programs HEU Minimization, Research Reactor Projects, Fuel Return Program | J. Dewes | IAEA | HEU Minimization Programs |
| S1-P2 | HEU Minimization in Japan | M. Sato | MEXT/Japan | HEU Minimization Programs |
| S1-P3 | Fireside Chat: Offices of Conversion and Nuclear Material Removal | C. Landers T. Blanchard-Case |
NNSA/US | HEU Minimization Programs |
| S1-P4 | Proliferation Resistance Optimization (PRO-X) Overview | A. Meehan | NNSA/US | HEU Minimization Programs |
| S2-P1 | Subcritical Experiment Using U-7Mo LEU Fuel at KUCA Facility [posted:
Oct. 04, 2022] View Paper |
H. Unesaki | Kyoto University/ Japan |
Proliferation Resistance Now and for the Future |
| S2-P2 | Present Status of UTR-KINKI and Preliminary Feasibility Study on its Future Conversion to Low-Enriched Fuel [posted: Oct. 04, 2022] | G. Wakabayashi | Kindai/Japan | Proliferation Resistance Now and for the Future |
| S2-P3 | Nigeria Research Reactor-2 (NIRR-2) Project Perspectives on Proliferation Resistance [posted: Oct. 05, 2022] | S. Jonah | CERT/Nigeria | Proliferation Resistance Now and for the Future |
| S2-P4 | INVAP Perspectives and Initiatives for Proliferation Resistance as Research Reactors Designer [posted:
Oct. 04, 2022] View Paper |
D. Ferraro | INVAP/ Argentina |
Proliferation Resistance Now and for the Future |
| S2-P5 | IAEA Support to New Research Reactor Progammes: Planning for Sustained Utilization [posted: Oct. 04, 2022] | N. Barradas | IAEA | Proliferation Resistance Now and for the Future |
| S3-P1 | Integration of Fuel Testing and Fabrication Efforts to Support Regulatory Qualification of LEU U-10Mo Monolithic Fuel | J.I. Cole | INL/US | Panel: Qualification and Fabrication of Sustainable Fuel |
| S3-P2 | Overview of Research Reactor Fuel Development at KAERI [posted: Oct. 05, 2022] | J.M. Park | KAERI/Korea | Panel: Qualification and Fabrication of Sustainable Fuel |
| S3-P3 | Framatome CERCATM sustainability of LEU fuel fabrication [posted: Oct. 05, 2022] | D. Geslin | CERCA/France | Panel: Qualification and Fabrication of Sustainable Fuel |
| S3-P4 | Facilitated discussion among the three panelists to inject interplay of fuel fab constraints and QC and relationship to fuel qualification campaigns | Panel: Qualification and Fabrication of Sustainable Fuel | ||
| S4-P1 | Licensing Process of a New Fuel Type Element in Poland on an Example of the Experimental Fuel Element for Samples Irradiation in the Fast Neutron Spectrum [posted:
Oct. 05, 2022] View Paper |
M. Lipka | NCBJ/Poland | Fuel Qualification and Irradiation Campaigns |
| S4-P2 | Developments of High-density Atomized U3Si2 Fuel Plates in KAERI [posted: Oct. 05, 2022] | T.W. Cho | KAERI/Korea | Fuel Qualification and Irradiation Campaigns |
| S4-P3 | Update of Fuel Meat Swelling Determination of Coated-(U-7Mo)/Al Dispersion Fuel from EMPIrE [posted: Oct. 05, 2022] | B. Ye | ANL/US | Fuel Qualification and Irradiation Campaigns |
| S4-P4 | New Results from the Scanning Electron Microscopy Characterization of Fuel Plates Irradiated in the EMPIrE Irradiation Experiment [posted:
Nov. 09, 2022] View Paper |
D. Keiser | INL/US | Fuel Qualification and Irradiation Campaigns |
| S4-P5 | Post-irradiation Optical Microscopy, Chemical Burn-up Analysis, and Blister Threshold Testing of the MP-1 Irradiation Experiment | A. Robinson | INL/US | Fuel Qualification and Irradiation Campaigns |
| S4-P6 | Design of the University of Missouri Design Demonstration Element Test for Irradiation in the Advanced Test Reactor [posted: Oct. 05, 2022] | I. Glagolenko | INL/US | Fuel Qualification and Irradiation Campaigns |
| S5-P1 | Status and Plans of U.S. U-10Mo Fuel Fabrication | C. Lavender | PNNL/US | Fuel Fabrication Challenges and Advances |
| S5-P2 | USHPRR HFIR Silicide Fabrication Update [posted:
Oct. 05, 2022] View Papers: A Robust Processing Approach for Producing Highly Loaded Dispersion Fuels Forming Complex Nuclear Fuel Shapes in High-Loaded Silicide Surrogates |
Z. Huber | PNNL/US | Fuel Fabrication Challenges and Advances |
| S5-P3 | USHPRR Critical Characteristics [posted: Oct. 05, 2022] | P.T. Gee | PNNL/US | Fuel Fabrication Challenges and Advances |
| S5-P4 | U-Mo Bare Foil Rolling Progress for FRM II Conversion [posted: Oct. 05, 2022] | K. Buducan | TUM/Germany | Fuel Fabrication Challenges and Advances |
| S6-P1 | Fuel Plate Cladding Thickness Estimation Thanks to Acoustic Microscopy [posted:
Oct. 05, 2022] View Paper |
A. Megzari | U. Montpellier/ France |
Poster Session |
| S6-P2 | Effect of Heat Treatments on the Irradiation Behavior of Monolithic U-Mo Fuels [posted: Oct. 05, 2022] | J.-F. Jue | INL/US | Poster Session |
| S6-P3 | Development of Technology for Manufacturing of Dispersion Type Targets for Fission Mo-99 Production [posted: Oct. 27, 2022] | L. Olivares | CCHEN/Chile | Poster Session |
| S6-P4 | The HANARO Irradiation Test of Coated U-7Mo/Al-5Si Mini-plates | Y.J. Jeong | KAERI/Korea | Poster Session |
| S6-P5 | Identification and Assessment of the Hazards in a Nuclear Fuel Fabrication Facility with LEU | H. Elsayed | EAEA/Egypt | Poster Session |
| S6-P6 | Recent Developments in PLTEMP/ANL V4.3 Code for Research Reactor Thermal Hydraulics Analysis [posted: Oct. 05, 2022] | J. Licht | ANL/US | Poster Session |
| S6-P7 | The STAT7 V1.1 Code for Statistical Propagation of Uncertainties in Steady-State Thermal Hydraulics Analysis of Research Reactors [posted: Oct. 05, 2022] | E. Wilson | ANL/US | Poster Session |
| S6-P8 | Low Enriched Nuclear Fuel Based on Uranium-Zirconium Carbon-Nitride: Reactor Tests and Post-Reactor Studies [posted:
Oct. 05, 2022] View Paper |
S.N. Sikorin | JIPNR-Sosny/ Belarus |
Poster Session |
| S6-P9 | USHPRR MP-1 Irradiation Test: Assessment of Edge Pitting and Bond Line Corrosion in Vendor Produced Fuel Plates [posted: Oct. 05, 2022] | J. Giglio | INL/US | Poster Session |
| S6-P10 | Non-destructive Post-Irradiation Examination and Fuel Swelling Analysis of the MP-1 Irradiation Experiment [posted: Oct. 05, 2022] | A. Robinson | INL/US | Poster Session |
| S6-P11 | Assessment of Critical Data for Qualification of U-10Mo Monolithic Fuel [posted: Oct. 05, 2022] | W. Hanson | INL/US | Poster Session |
| S6-P12 | Fabrication Process Research and Development to Support HFIR LEU Silicide [posted: Oct. 11, 2022] | Z. Huber | PNNL/US | Poster Session |
| S6-P13 | Modeling of Thermal Conductivity in a Uranium Silicide Dispersion Fuel to Support Conversion of HFIR to LEU Fuels [posted: Oct. 06, 2022] | C. Lavender | PNNL/US | Poster Session |
| S6-P14 | Modeling Insights in Forming and Rolling Complex Geometries of Highly Loaded Uranium Silicide Dispersion Fuels [posted: Oct. 06, 2022] | C. Lavender | PNNL/US | Poster Session |
| S6-P15 | Recent Progress in U-10Mo Mechanical and Thermophysical Property Characterization [posted: Oct. 06, 2022] | J. Schulthess | INL/US | Poster Session |
| S6-P16 | Fine Mapping of the Power Density Distribution of MTR Fuel Using Gamma Spectroscopy [posted: Oct. 06, 2022] | G. Gabrieli | SNRC/Israel | Poster Session |
| S6-P17 | About the Limits of Optical Microscopy Measurement for Al-Fuel Cladding Thickness [posted: Oct. 06, 2022 ] View Paper | B. Stepnik | Framatome/ France |
Poster Session |
| S6-P18 | PRO-X Auxiliary Capabilities: Balancing Performance & Proliferation for Research Reactor Products | M.A. Brown | ANL/US | Poster Session |
| S7-P1 | U.S. High Performance Research Reactor LEU Conversion Design, Testing and Fabrication Progress | E. Wilson | ANL/US | U.S. High Performance Reactor Conversions |
| S7-P2 | High Flux Isotope Reactor Low-Enriched Uranium Conversion Activities – 2022 Status Update [posted: Oct. 05, 2022] | C. Sizemore | ORNL/US | U.S. High Performance Reactor Conversions |
| S7-P3 | Alternative HEU-LEU Mixed Core Transition Strategy for the MIT Research Reactor | L.-W. Hu | MIT/US | U.S. High Performance Reactor Conversions |
| S7-P4 | A Progress Update on the Highly Enriched Uranium to Low-Enriched Uranium Fuel Conversion at the University of Missouri Research Reactor [posted: Nov. 30, 2022] | M. Pinilla | MU/US | U.S. High Performance Reactor Conversions |
| S7-P5 | Analysis Methods for Lead Test Assemblies in the Advanced Test Reactor [posted: Oct. 05, 2022] | C. Clark | INL/US | U.S. High Performance Reactor Conversions |
| S7-P6 | NIST Neutron Source Preconceptual Design [posted:
Oct. 05, 2022] View Paper |
D. Sahin | NIST/US | U.S. High Performance Reactor Conversions |
| S8-P1 | Packaging of Critical Assembly Fuel Materials for Shipment in the ES-3100 [posted: Oct. 06, 2022] | T. Andes | CNS Y-12/US | HEU Removal Operations and Fuel Transportation |
| S8-P2 | The Role of Nuclear Criticality Safety in Enabling the Transport of Highly Enriched Uranium (HEU) (and Other Fissile Materials) to Support Global Strategic Removal Projects [posted:
Oct. 06, 2022] View Paper |
C. Davis | NTS/UK | HEU Removal Operations and Fuel Transportation |
| S8-P3 | Mobile Packaging Program Overview | J. Smith | NNSA/US | HEU Removal Operations and Fuel Transportation |
| S8-P4 | Nigerian Nuclear Regulatory Authority Experience on NIRR-1 Core Conversion from HEU to LEU Fuel [posted: Oct. 06, 2022] | G. Omeje | NNRA/Nigeria | HEU Removal Operations and Fuel Transportation |
| S9-P1 | Acceptance Test of WCTC with LEU Fuel at the IVG.1M Research Reactor Site in Kazakhstan [posted: Oct. 06, 2022] | I. Bolshinsky | INL/US | International Reactor Conversion Progress and Partnerships |
| S9-P2 | First Steps for the Optimization of Experimental Facilities at FRM II during Conversion [posted: Oct. 06, 2022] | D. Bonete-Wiese | TUM/Germany | International Reactor Conversion Progress and Partnerships |
| S9-P3 | RELAP5 Safety Analyses in Support of the BR2 COBRA Lead Test Assembly Irradiation [posted: Oct. 06, 2022] | F. Wols | SCK-CEN/ Belgium |
International Reactor Conversion Progress and Partnerships |
| S9-P4 | Benchmark between the MAIA and DART Fuel Performance Codes on the E-FUTURE U-Mo/Al Dispersion Fuel Test [posted:
Oct. 06, 2022] View Paper |
S. Valance | CEA/France | International Reactor Conversion Progress and Partnerships |
| S9-P5 | Water Channel Thickness Estimation through High Frequency Ultrasonic Measurements [posted:
Oct. 06, 2022] View Paper |
R. Mrabti | U. Montpellier/ France |
International Reactor Conversion Progress and Partnerships |
| S10-P1 | Identification of Relevant Parameters for the Structural Analysis of an Involute LEU Fuel Plate | A. Bergeron | ANL/US | Design and Analysis Methods |
| S10-P2 | First Steps Towards the Development of a Tool for Sensitivity Analysis and Uncertainty Propagation Studies for Steady-State Thermal-Hydraulic Simulations of Research Reactors [posted: Oct. 06, 2022] | R. Schönecker | TUM/Germany | Design and Analysis Methods |
| S10-P3 | Improvements to Thermal-Hydraulics Models and Methods for MTR-Type Reactors [posted: Oct. 06, 2022] | M. Nasso | INVAP/ Argentina |
Design and Analysis Methods |
| S10-P4 | Neutronic Simulation of Curved Fuel Plate with Flat Plate Geometry [posted:
Oct. 06, 2022] View Paper |
L.-Y. Cheng | BNL/US | Design and Analysis Methods |
| S10-P5 | Process Modeling of U-10Mo and U3Si2 Using Integrated Computational Materials Engineering | C. Lavender | PNNL/US | Design and Analysis Methods |
| S11-P1 | Physical Start-up of IVG.1M Reactor with Low-Enriched Uranium Fuel [posted: Oct. 06, 2022] | I.V. Prozorova | NNC/ Kazakhstan |
Licensing and Conversion Reactor Experience |
| S11-P2 | Six-Year Experience of the WWR-K Reactor Operation with LEU Fuel [posted: Oct. 06, 2022] | A. Shaimerdenov | INP/ Kazakhstan |
Licensing and Conversion Reactor Experience |
| S11-P3 | Practical Application of LEU Fuel for NIRR-1 Safe Operation [posted: Oct. 06, 2022] | K.J. Adedoyin | NNRA/Nigeria | Licensing and Conversion Reactor Experience |
| S11-P4 | Utilization and Operation of the Dalat Nuclear Research Reactor after Full Core Conversion [posted: Oct. 06, 2022] | K.C. Nguyen | VINATOM/ Vietnam |
Licensing and Conversion Reactor Experience |
| List last updated Feb. 13, 2023 | ||||
Questions?
Please address inquiries about the RERTR-2022 technical program to the Meeting organizer, John Holland.
Last Modified: Tue, October 4, 2022 12:23 PM
