Argonne National Laboratory
RERTR-2019
International Meeting on Reduced Enrichment for Research and Test Reactors
RERTR Program, Nuclear Science and Engineering Division at Argonne
U.S. Department of Energy

RERTR-2019 International Meeting

Oct. 6-9, 2019, Zagreb, Croatia


RERTR-2019 Technical Program

Download the RERTR-2019 Technical Program by clicking on the image above.

Available Abstracts and Papers

The available abstracts and/or papers that were presented at the “40th RERTR 2019 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, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, 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.

# Paper/Presentation Title Presenter Affiliation Topic
  Opening Remarks W. R. Kohorst US Embassy Zagreb  
  Welcome to 40th International RERTR Meeting P. Kearns ANL  
S1-P1 NNSA Nonproliferation Initiatives and Partnerships B. Park DOE-NNSA Global Progress in HEU Minimization
S1-P2 International Atomic Energy Agency Efforts to Promote Nuclear Nonproliferation C. Xerri IAEA Global Progress in HEU Minimization
S2-P1 Reactor Conversion by the Numbers C. Landers

DOE-NNSA

HEU Minimization Structures Plenary
S2-P2 Nuclear Material Removal Collaboration with Research Reactor Conversions S. Roecker

DOE-NNSA

HEU Minimization Structures Plenary
S2-P3 IAEA and RERTR: A History of Collaboration F. Marshall IAEA HEU Minimization Structures Plenary
S3-P1 Technical Highlights from 40 RERTR Conferences and Reactor Conversions J. Stevens ANL Life After Conversion I
S3-P2 Framatome-CERCA™ Successes in Research Reactor Conversions F. Gauche   Life After Conversion I
S3-P3 Status of Hungary after the HEU-LEU Conversion
Paper [posted: Nov. 25, 2019]
I. Vidovszky Centre for Energy Research Life After Conversion I
S4-1 Towards a HEU-free World: INVAP’s Experience, Challenges, Milestones, and Perspective M. G. Marquez INVAP S.E. Life After Conversion II
S4-P2 Support of ÚJV Řež, a. s. for Shipments of Spent Nuclear Fuel within the M3 Program
Paper [posted: Nov. 25, 2019]
J. Podlaha ÚJV Řež Life After Conversion II
S4-P3 Comparison of Thermal Hydraulics Characteristics of NIRR-1 LEU Core with HEU Core S. Jonah Nigeria Atomic Energy Commission Life After Conversion II
S5-P1 History of the U.S. Origin Program and Its Current End State
Paper [posted: Nov. 25, 2019]
J. Galan Savannah River Site HEU Removal Operations and Fuel Transportation
S5-P2 Current Status of the Russian Research Reactor Fuel Return Program I. Bolshinsky INL HEU Removal Operations and Fuel Transportation
S5-P3 NAC’s OPTIMUS™ Packaging for Research Reactor Wastes
Paper [posted: Nov. 25, 2019]
J. England NAC International HEU Removal Operations and Fuel Transportation
S5-P4 Impacts to the Advanced Test Reactor Fresh Fuel Shipping Container (ATR FFSC) for the Transport of LEU Fuel K.A. Dunn Savannah River National Laboratory HEU Removal Operations and Fuel Transportation
S5-P5 Corrosion Protection of Spent Aluminum-Clad Research Reactor Fuel During Long Term Wet Storage
Paper [posted: Nov. 25, 2019]
L.V. Ramanathan IPEN HEU Removal Operations and Fuel Transportation
S6-P1 Calculated Studies in Support of the Creation of a Uranium-Zirconium Hydride Critical Assembly with Low Enriched Uranium Zirconium Carbonitride Fuel
Paper [posted: Nov. 25, 2019]
S. Sikorin Joint Institute for Power and Nuclear Research – Sosny Poster Session
S6-P2 USHPRR Fuel Fabrication Pillar Fabrication Process Status R.B. Nielson INL Poster Session
S6-P3 Current Status on the Development of High-density LEU U3Si2 Fuel in KAERI Y.J. Jeong KAERI Poster Session
S6-P4 Update of Regulatory Oversight of NIRR-1 Core Conversion K. Adedoyin Nigerian Nuclear Regulatory Authority Poster Session
S6-P5 European Developments for Monolithic UMo Fuel: UMo Foil Manufacturing Project S. Lorand Framatome – CERCA™ Division Poster Session
S6-P6 Depleted Uranium Manufacturing Studies for KUCA LEU Conversion Fuels J. Allenou Framatome – CERCA™ Division Poster Session
S6-P7 Y-12 National Security Complex LEU-Mo Casting Update D. Turpin Y-12 National Security Complex Poster Session
S6-P8 First-Principles Study of Surface Properties of Crystalline and Amorphous Uranium Aluminides A.M. Yacout ANL Poster Session
S6-P9 Microstructural Characterization of U-7Mo Dispersion Fuel Plates Irradiated at High Power D. Keiser INL Poster Session
S6-P10 Fabrication of Atomized LEU-7wt.%Mo Powder for KUCA Core Conversion K. Lee

KAERI

Poster Session
S6-P11 Transition Cores Accident Analyses for the Conversion of the University of Missouri Research Reactor from Highly Enriched to Low-Enriched Uranium D.S. Yoon ANL Poster Session
S6-P12 UMo Benchmark Experiment Data Needed to Support Computational and Nuclear Data Validation
Paper [posted: Nov. 25, 2019]
M.A. Marshall INL Poster Session
S6-P13 Scale-Up of Atomic Layer Deposition Coating and Heat Treatment of Uranium-Molybdenum Powder L. Jamison ANL Poster Session
S6-P14 DART Simulation of Plate-Type Fuels to High Burnup G. Hofman ANL Poster Session
S6-P15 Microstructure-Based Process Modeling and Integration of U-10Mo V. Joshi PNNL Poster Session
S6-P16 Evaluation of Fuel Swelling and Irradiation Creep Behavior for a MURR LEU U-10Mo Monolithic Plate: A Finite Element Analysis Based Study W. Mohamed ANL Poster Session
S6-P17 Verification and Validation of Thermal-Hydraulic Analysis Software: The University of Missouri Research Reactor as a Case Study D.S. Yoon ANL Poster Session
S7-P1 Status of KJRR Fuel Qualification - Update J.M. Park KAERI LEU Fuel Design and Qualification
S7-P2 Review on the Development of Very High Density Fuels by CMAD Group M. Lopez CNEA LEU Fuel Design and Qualification
S7-P3 SEMPER FIDELIS: Post Irradiation Examination Results A. Leenaers SCK·CEN LEU Fuel Design and Qualification
S7-P4 Non-Destructive Examination Preliminary Results of EMPIrE A.B. Robinson INL LEU Fuel Design and Qualification
S7-P5 A Qualification Base Report on High-Density U3Si2/Al Dispersion Fuel for High-Power Research Reactors Y.S. Kim ANL LEU Fuel Design and Qualification
S7-P6 Status of LEU U-10Mo Monolithic Fuel Testing and Qualification Efforts to Support US High Performance Research Reactor Conversions J. Cole INL LEU Fuel Design and Qualification
S8-P1 USHPRR Fuel Fabrication Pillar Fabrication Status, Process Optimizations and Future Plans C.A. Lavender PNNL Fuel Fabrication Technology
S8-P2 Y-12 Past, Present and Future Supplying Uranium
Paper [posted: Nov. 25, 2019]
L. Jollay Y-12 National Security Complex Fuel Fabrication Technology
S8-P3 USHPRR Fuel Element Specifications and Plate Demonstration Plans D. Jaluvka ANL Fuel Fabrication Technology
S8-P4 Impact Assessment for the MIT Research Reactor LEU Fuel Fabrication D. Allen MIT Nuclear Reactor Laboratory Fuel Fabrication Technology
S8-P5 Manufacturing of the HiPROSIT Irradiation Experiment: High density U3Si2 Fuel Plates B. Stepnik Framatome – CERCA™ Division Fuel Fabrication Technology
S8-P6 Future HALEU Supply – A Front-end Industrial Actor’s View J-B. Darphin ORANO Fuel Fabrication Technology
S9-P1 US High Performance Research Reactor LEU Conversion Design and Qualification Progress E.H. Wilson ANL High Performance Reactor Conversions
S9-P2 Progress Update on the MIT Research Reactor (MITR) Conversion from Highly Enriched Uranium to Low Enriched Uranium Fuel L. Hu MIT Nuclear Reactor Laboratory High Performance Reactor Conversions
S9-P3 Conversion Status of the University of Missouri-Columbia Research Reactor from Highly Enriched to Low-Enriched Uranium Fuel L. Foyto University of Missouri-Columbia Research Reactor High Performance Reactor Conversions
S9-P4 Recent Work on Conversion of the NIST Research Reactor T.H. Newton NIST Center for Neutron Research High Performance Reactor Conversions
S9-P5 Present Status of the ATR LEU Fuel Project and the Element Test Campaign J. Jenkins INL High Performance Reactor Conversions
S9-P6 High Flux Isotope Reactor Conversion from High-Enriched to Low-Enriched Uranium Fuel – A 2019 Progress Update P.K. Jain ORNL High Performance Reactor Conversions
S10-P1 History and Current Status of the KUCA Dry Core Conversion Project
Paper [posted: Nov. 25, 2019]
J. Morman ANL International Conversion Progress, LEU Reactor Development and Post-Conversion Performance
S10-P2 Status of the IVG.1M Fuel Test V.S. Gnyrya IAE Branch of NNC International Conversion Progress, LEU Reactor Development and Post-Conversion Performance
S10-P3 Experimental and Analytical Transient Studies of Material Movements Inside Critical Configurations Using Low Enriched Uranium Fuel Y. Gohar ANL International Conversion Progress, LEU Reactor Development and Post-Conversion Performance
S10-P4 Non-Reactor Tests of HEU and LEU Fuel and Reflector Material (Beryllium Oxide) as Part of the IGR Reactor Conversion Y. Baklanova IAE Branch of NNC International Conversion Progress, LEU Reactor Development and Post-Conversion Performance
S10-P5 Progress of the Kijang Research Reactor (KJRR) Project in Korea H-S. Jung KAERI International Conversion Progress, LEU Reactor Development and Post-Conversion Performance
S11-P1 High-Temperature FLiBe Salt and Materials Irradiation Tests Supporting Molten Salt Reactors Development at the MIT Research Reactor L. Hu MIT Nuclear Reactor Laboratory Fuel Irradiation Testing and Characterization
S11-P2 Low Enrichment Nuclear Fuel Based on Uranium-Zirconium Carbonitride: Performance of the Methodical Reactor Experiment A. Bakhin Scientific Research Institute Scientific Industrial Association "LUCH" Fuel Irradiation Testing and Characterization
S11-P3 Current Plans for Irradiation Testing of Low Enriched Uranium Silicide Fuel in Support of High Flux Isotope Reactor (HFIR) Conversion I. Glagolenko INL Fuel Irradiation Testing and Characterization
S11-P4 Overview and Status of the FUTURE-HFIR Irradiation Experiment W.F. Jones INL Fuel Irradiation Testing and Characterization
S11-P5 Design of Full Size Plate Irradiation Test for U-10Mo Monolithic Fuel Qualification M.A. Marshall INL Fuel Irradiation Testing and Characterization
S11-P6 A Transmission Electron Microscopy Study of Low Burnup U-7Mo Samples D. Salvato SCK·CEN Fuel Irradiation Testing and Characterization
S12-P1 Projection of Irradiation Behavior of U3Si2 Dispersion Fuel at High Fuel Loading and High Operating Power
Paper [posted: Jul. 22, 2020]
G. Hofman ANL Fuel Performance Measurement Analysis and Modeling
S12-P2 Evaluation of the Thickness of PVD-Deposited Mo, Zr Coatings as Diffusion Barriers Between U-Mo and Al Using Heavy Ion Irradiation J. Shi FRM II Fuel Performance Measurement Analysis and Modeling
S12-P3 Fission Product Release Testing to Support Qualification of an LEU Fuel for the Advanced Test Reactor
Paper [posted: Nov. 25, 2019]
K. Metzroth MPR Associates Fuel Performance Measurement Analysis and Modeling
S12-P4 Operational Effects of the BR2 Driver Fuel Transition G. Newman SCK·CEN Fuel Performance Measurement Analysis and Modeling
S12-P5 Attaining Uniform Thickness of U-10Mo and Zr in Monolithic Fuel V. Joshi PNNL Fuel Performance Measurement Analysis and Modeling
S12-P6 Review of the Technical Basis for Properties and Fuel Performance Data Used in USHPRR HEU to LEU Conversion Analysis Compared to the Preliminary UMo Report L. Jamison ANL Fuel Performance Measurement Analysis and Modeling
S13-P1 Non-parametric Statistical Safety Analysis Tools to Support ATR Conversion to LEU
Paper [posted: Nov. 25, 2019]
B. Hallee MPR Associates

Conversion and Systems Analyses

S13-P2 Safety Analysis of the IVG.1M Reactor with LEU Fuel R.A. Irkimbekov IAE Branch of NNC Conversion and Systems Analyses
S13-P3 Computational Codes Developed by RERTR for LEU Conversion and Used at Research and Test Reactors Worldwide J.R. Licht ANL Conversion and Systems Analyses
S13-P4 Overview of Beyond Design Studies Performed within the Framework of BR2 Decennial Safety Review F.J. Wols SCK·CEN Conversion and Systems Analyses
S13-P5 Four Design Demonstration Elements (DDEs) to be Irradiated in the Advanced Test Reactor (ATR) and Belgian Reactor 2 (BR2) G.K. Housley INL Conversion and Systems Analyses
S13-P6 Involute Working Group – Progress towards Validation of CFD for Involute-Plate Reactors Safety Analysis A. Bergeron ANL Conversion and Systems Analyses
List last updated Jul. 22, 2020

Questions?

Please address inquiries about the RERTR-2019 technical program to the Meeting organizer, John Holland.

Last Modified: Mon, November 25, 2019 5:10 PM

2019 RERTR Meeting

The 2019 International RERTR Meeting (RERTR-2019) was held in Zagreb, Croatia on October 6-9, 2019.

RERTR-2019 News:

Nov. 25, 2019 First set of papers available: A first set of papers from the RERTR-2019 International Meeting in Edinburgh is now available for downloading...Download Papers


Sep. 18, 2019 Technical Program: The technical program for RERTR-2019 is now available…Download Technical Program


Jul. 18, 2019RERTR-2019: Announcing RERTR-2019… Details

For more information:

Technical Questions:
For further information and questions please contact:

John Holland
Argonne National Laboratory
email
See also Program Committee

Administrative Questions:
Karen Grudzinski
Argonne National Laboratory
9700 South Cass Avenue, Building 208
Argonne, Illinois 60439-4842
Phone: +1 (630) 252-1671
Fax: +1 (630) 252-5161
email:

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