2009 International RERTR Meeting

Abstracts and Available Papers Presented at the Meeting

The “31^th RERTR 2009 International Meeting on Reduced Enrichment for Research and Test Reactors” was held in Beijing, China from November 1-5, 2009. The available abstracts and papers that were presented at this meeting are provided below.

Welcome to China and RERTR-2009

• A Welcome from the President of the China Institute of Atomic Energy
  Zhao ZhiXiang

Open Programmatic Remarks

• An Overview of the NNSA Global Threat Reduction Programs Goals for HEU Minimization
  A. Bieniawski
• International Atomic Energy Agency Programs Supporting HEU Minimization
  P. Adelfang

International Perspectives and Progress on HEU Minimization

• S1-P1 A Road Map for HEU Clean-Out  Future Objectives of HEU Minimization – The Norwegian Perspective
  O. Reistad, S. Hustveit, W. Beere
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 70KB]
• S1-P2 Current Status of Reduced Enrichment Program for Research Reactors in Japan
  H. Unesaki, T. Kitamura
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 82KB]
• S1-P3 HEU Minimization Programs Status and Plans at IAEA
  P. Adelfang
• S1-P4 The United States Research Reactor (FRR) Spent Nuclear Fuel (SNF) Acceptance Program - 2009 Update
  C. Messick, J. Taylor, M. Niehus
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 47KB]
• S2-P1 New Strategies for HEU Minimization
  M. Pomper, C. Hansell, W. Potter
• S2-P2 2009 Progress Report on RERTR Activities in Argentina
  S. Balart,  P. Cristini,  A. Gonzalez, R.González, J. Hermida, M. López, M. Mirandou, H. Taboada
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 47KB]
• S2-P3 Core Conversion Scenario of the Budapest Research Reactor
  S. Tőzsér, J. Gadó, I. Benkovics
• S2-P4 Status of the U.S. Domestic Reactor Conversion Program
  E. Woolstenhulme, D. Hewit
• S2-P5 AREVA-CERCA A Committed Support to His Partners to Succeed GTRI Program 
  C. Jarousse, N. Franck, P. Colomb, L. Halle, A. Kocher, J. Macias
  

International Programs and Perspectives on Fuel Development

• S3-P1 US Progress in LEU Fuel Development
  D. Wachs
• S3-P2 Current Status of the Development of High Density LEU Fuel for Russian Research Reactors
  A. Vatulin, I. Dobrikova, V. Suprun, G. Kulakov, A. Izhutov, E. Novoselov, V. Alexandrov, A. Ykovlev, V. Shishin
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 1.1MB]
• S3-P3 The Development Status of U-Mo Alloy Fuel in NPIC
  C. Yin, J. Chen, C. Sun, Y. Liu
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 276KB]
• S3-P4 The LEONIDAS and US Partnership for UMo Dispersion Fuel Qualification
  E. Koonen, H.Guyon, P. Lemoine, C. Jarousse, D. Wachs, J. Stevens
• S3-P5 Method of Utilizing the Stabilizing Effect of Silicon in U-Mo-Al Dispersion Fuel and Minimum Si Addition Required for Given Operating Conditions
  G. Hofman, Y-S. Kim, A. Robinson

Conversion Experience and Planning

• S4-P1 RA-6 Reactor Conversion and Neutronic Tests of the New Silicides Fuel Core
  H. Blaumann, J. Longhino, F. Sánchez, E. Lopasso, F. Lezczscynski, D. Ferraro, F. Brollo, C. Fernández, A. Gómez, P. Bellino
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 161KB]
• S4-P2 Conversion of the Oregon State University TRIGA Reactor from HEU Fuel to LEU Fuel
  S. Keller, S. Reese
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 173KB]
• S4-P3 Plan of WWR-K Reactor Conversion to LEU Fuel
  F. Arinkin, Sh. Gizatulin, S. Koltochnik, A. Tuleushev, P. Chakrov, L. Chekushina, P. Garner, N. Hanan, J. Roglans-Ribas
• S4-P4 Irradiation Testing of the LEU Fuel in MARIA Research Reactor
  G. Krzysztoszek and K. Pytel
• S4-P5 Preliminary Results of Full Core Conversion from HEU to LEU of the Dalat Nuclear Research Reactor
  P. Lam, L. Vinh, H. Nghiem, N. Cuong, L. Vien
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 525KB]
• S4-P6 Enrichment Reduction Possibility for MEPHI Research Reactor
  V. Alferov, E. Kryuchkov, M. Shchurovskaya
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 136KB]

Fuel Development - Irradiation Testing

• S5-P1 Results of the IRIS4 Irradiation in OSIRIS Reactor
  M. Ripert, F. Charollais, M. C. Anselmet, X. Tiratay, P. Lemoine
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 1.1MB]
• S5-P2 The Status of LEU U-Mo Fuel Investigation in the MIR Reactor
  A. Izhutov, V. Alexandrov, A. Novosyolov, V. Starkov, A. Sheldyakov, V. Shishin, V. Yakovlev, I. Dobrikova, A. Vatulin, V. Suprun, Ye. Kartashov, V. Lukichev
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 3.8MB]
• S5-P3 Qualification of the BR2-EVITA Loop and Irradiation of the First JHR Lead Test Assembly
  P. Lemoine, M. Anselmet, E. Koonen, Ph. Benoit, Ph. Gouat, G. Miras, S. Brisson
  
• S5-P4 Irradiation Performance of U-Mo alloy Based ‘Monolithic’ Plate-type Fuel Design Selection
  A. Robinson, G. Chang, D. Keiser, D. Wachs, and D. Porter
• S5-P5 Effect of Burnup and Irradiation Temperature on Crystalline Phase Evolution in Al-UMo Dispersion Fuel
  D. Sears, B. Leitch, G. Edwards, I. Swainson, R. Rogge

Fuel Development Poster Session

• S6-P1 Manufacturing and Characterization of LEU Dispersion Miniplates Based on Hydrided Powders
  L. Olivares, J. Marin, J. Lisboa and M. Barrera
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 1.4MB]
• S6-P2 A Library of LEU Fuel Materials Properties for Research Reactors
  T. Totev, G. Hofman J. Rest, Y. Kim, M. Looby, D. Burkes, D.Wachs, M. Meyer, S. Hayes
• S6-P3 Current Activities in the Out of Pile Investigations of the Interaction Between UMo and Al or Al Alloys
  S. Balart, L. Kniznik, C. Komar Varela, P. Gargano, M. Mirandou, S. Aricó, P. Alonso, G. Rubiolo, A. Fortis, L. Gribaudo
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 266KB]
• S6-P4 Characterization of the Diffusion Layer in U-Mo/Zr-4 Diffusion Couple
  J. Chen, C. Yin, C. Sun, Y. Liu
• S6-P5 Optimization of a Pressure-Sintering Formation Process for a Plate Fuel with Single-Layer - Arraying U-Mo Large Particles and a Preliminary Fabrication of Fuel Micro-Plate
  C. Kim, S. Jang, H. Ryu, J. Park, K-H. Choi
• S6-P6 SEM and TEM Characterization of As-Fabricated U-Mo Dispersion Fuel Plates
  D. Keiser, Jr., B. Yao, E. Perez, Y.H. Sohn
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 474KB]
• S6-P7 Characterization of Interaction Layer in U-Mo/Al Diffusion-Couple
  Y. Liu, C. Yin, C. Sun, J. Chen
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 558KB]
• S6-P8 Implementation of RELAP5-3D System Model to Supplement the Design of the Hydro-Mechanical Fuel Test Facility
  W. Marcum, A. Arnold, B. Woods, D. Wachs
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 397KB]
• S6-P9 The Applications of Spatially Resolved Positron Annihilation Spectroscopy to RERTR Fuel Plates
  M. Okuniewski, and D. Akers
• S6-P10 An Integrated Approach to the Mechanical Behavior of U-Mo Monolithic Fuel
  M. Okuniewski, D. Wachs, D. Burkes, R. Prabhakaran,  F. Rice, P. Medvedev
• S6-P11 Interdiffusion in Diffusion Couples: U-Mo vs.Al and Al-Si
  E. Perez, B. Yao , Y. Sohn, D. Keiser
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 1.4MB]
• S6-P12 U-Mo Plate Blistering
  F. Rice, D. Wachs, A. Robinson, R. Lind
• S6-P13 Processes to Obtain Metallic Uranium from UF6 
  P. Rojas, H. Contreras, A. Garrao,  F. Valdés
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 263KB]
• S6-P14 Fabrication of Coated U-Mo Powder and the Effect of Si Content on the Interaction Layer Growth
  H. Ryu, J. S. Park, J. Shim, Y. Lee, J. M. Park, C. Kim
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 1.5MB]
• S6-P15 Irradiation Testing of Full-Size Dispersion and Monolithic Fuel Plates in the ATR
  D. Wachs, D. Utterbeck, J. Wight, G. Chang, M. Lillo, G. Roth, J. Williams, S. Taylor, R. Ambrosek, M. Drigert, N. Kraft,  A. Robinson
• S6-P16 Study on In-Pile Performance of Silicide Fuel Under Power Transient
  K. Yanagisawa
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 685KB]
• S6-P17 Recent Progress in Plasma Spaying, Plate Forming and HIP Can Development for Monolithic Fuel Plate Fabrication
  D. Dombrowski, K. Hollis, D. Alexander, K. Clarke, P. Hochanadel, P. Burgardt, A. Duffield, M. Pena, J. Katz
• S6-P18 Corrosion of Aluminum Alloys in Water at Temperatures up to 100 ºС
  O. Golosov
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 280KB]
• S6-P19 Advances in the Study of High Density Fuels in CNEA
  M. López, R. González, A. González, H. Taboada

Mo-99 Production Development

• S7-P1 Installation and Commissioning a New LEU Based Mo-99 Plant in Australia
  M. Druce
• S7-P2 Overview of Argonne Progress in Developing LEU-Based Processes for the Production of Mo-99
  G. Vandegrift, D. Stepinski, A. Ziegler, E. Krahn, J. Fortner, K. Quigley, C. Mertz, S. Chemerisov, J. Jerden Jr., A. Hebden, A. Guelis, and A. Bakel
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 178KB]
• S7-P3 On a New Way of Large-Scale Mo-99 Production in Molten Salt Fluoride Fuel
  D. Chuvilin, V. Zagryadskiy
• S7-P4 Update on Operational Experience of Zirconium Molybdate –  Mo-99 Gel Generator Production in India
  S. Sarkar, C. Kothalkar, P. Naskar, P. Saraswathy, A.Dey, A. Kohli, V.Meera, V. Venugopal
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 124KB]
• S7-P5 Fostering Additional Sources of Molybdenum-99 Production for Supporting Nuclear Medicine Services and Progress in the IAEA CRP on Molybdenum Production from LEU or Neutron Activation
  N. Ramamoorthy, I. Goldman, P. Adelfang

US High Performance Reactor Conversion

• S8-P1 Completion of Feasibility Studies on Using LEU Fuel in MIT Reactor
  T.H. Newton, Jr., L-W Hu, G. E. Kohse, E. E. Pilat, B. Forget, P. K. Romano, S. Wong, Y. Wang
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 119KB]
• S8-P2 Summary of the University of Missouri Research Reactor HEU to LEU Conversion Feasibility Study
  J. McKibben, K. Kutikkad, L. Foyto, B. Dionne, E. Feldman, J. Stevens, J. Stillman
• S8-P3 LEU Conversion Activities at the High Flux Isotope Reactor-Simplifying the Foil Design - Preparing the Reactor
  R. Primm, III, G. Ilas, J. Sease, J. Miller, T. Guida
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 322KB]
• S8-P4 Conversion of the NIST Research Reactor-Maintaining Core Geometry to Avoid a Startup Core
  R. Williams, W. Richards, S. O’Kelly, J. Michael Rowe, D. Diamond, A. Hanson, L-Y. Cheng,  A. Cuadra
• S8-P5 ATR PDQ and MCWO Fuel Burnup Analysis Codes Evaluation
  G. Chang, P. Roth, M. Lillo
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 535KB]

Fuel Development - Fabrication

• S9-P1 Fuel Fabrication Capability (FFC) Project
  D. Dombrowski
• S9-P2 Monolithic Fuel Fabrication Process Development at the Idaho National Laboratory
  G. Moore, F. Rice, N. Woolstenhulme, J-F. Jue, B. Park, S. Steffler, N. Hallinan, M. Chapple, M.C. Marshall, B.L. Mackowiak, C.R. Clark and B.H. Rabin
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 371KB]
• S9-P3 Update on Uranium-Molybdenum Fuel Foil Fabrication Development Activities at the Y-12 National Security Complex
  A. DeMint, J. Gooch, H. Longmire, T. Andes
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 487KB]
• S9-P4 Pyrochemical Recovery of Uranium from Monolithic U-10Mo Fuel Scrap
  J. Figueroa, M. Williamson, A. Bakel, and G. Vandegrift
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 411KB]

HEU Minimization in Sub-Critical Facilities

• S10-P1 Yalina-Booster Facility Performance with Low Enriched Uranium
  Y. Gohar, A. Talamo, I. Bolshinsky, H. Kiyavitskaya
• S10-P2 Neutron Source on the Base of Sub-Critical Assembly Driven by Linear Accelerator
  I. Karnaukhov, A. Zelinsky, I. Neklyudov, V. Krasnorutzkiy
• S10-P3 The Sub Critical Core of IPEN-MB-01 Driven by a Neutron Source in The Framework of the IAEA Collaborative Work on Low Enrichment Uranium(LEU) Fuel Utilization in Accelerator Driven Sub Assembly System
  J. Maiorino, T. Carluccio
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 649KB]
• S10-P4 Fuel Cycle Analyses of the KIPT Neutron Source Facility With Low Enriched Uranium Fuel
  Z. Zhong and Y. Gohar
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 1.2MB]

Minimization, Transportation and Fuel Disposition

• S11-P1 Experience in Certification of Transportations Under RRRFR Program
  A. Buchelnikov
• S11-P2 Thermal Decay Heat of High Enriched Uranium Spent Nuclear Fuel of TAJOURA Nuclear Research Reactor
  F. Bsebsu
• S11-P3 Approaches and Methods to Ensure Safety of International Transport of Russian Research Reactor SNF
  S. Komarov, M. Baryshnikov, B. Kanashov and A. Smirnov, A. Buchelnikov
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 539KB]
• S11-P4 Shipment of Spent Nuclear Fuel (SNF) From Badan Tenaga Nuklir National Reactor in Serpong-tangrang Indonesia to the Savannah River Site in Aiken SC
  E. Parker, C. Messick, I. Suryantoro, T. Andes, M. Valenzano
• S11-P5 Loading and Utilization of NAC-LWT at Research and Test Reactor Facilities
  J. Adam

Mo-99 Production - Technology Development

• S12-P1 Engineering of LEU-Foil Based Mo-99 Target for High Volume Production
  G. Solbrekken, K. Turner, C. Allen
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 697KB]
• S12-P2 Alternative Methods for Digesting Irradiated LEU Foil Targets to Produce Mo-99 in Alkaline Media
  A. Guelis, A. Bakel, J. Jerden, K. Quigley and G. Vandegrift, M. Precek
• S12-P3 A Simple, Inexpensive and User-friendly Technigue for Separation of Tc-99m from Mo-99 Produced by Neutron Activation of Mo-98 via the Mo-98(n,g)Mo-99
  S. Chattopadhyay, S. Saha Das and L. Barua
• S12-P4 Modeling of Excessive Power Accidents for a Proposed Research Reactor in Core Fission Mo-99 Production
  M. Gaheen, M. Shaat
• S12-P5 An Evaluation of Mo-99 Target Waste Proliferation Risks
  F. Dalnoki-Veress, C. Hansell, M. Pomper

HEU Minimization Poster Session

• S13-P1 Scrap Recovery for Fabrication of U-10Mo Fuel for High Performance Reactors
  A. Ziegler, L. Maggos, D. Stepinski, A. Bakel, and G. Vandegrift
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 72KB]
• S13-P2 Combating Illicit Trafficking of Nuclear Materials in Kenya
  S. Kiti, R. Kinyua
• S13-P3 Realization of Mixed Core Configurations in Core Conversion for the DALAT Nuclear Research Reactor
  P. Lam, N. Dien, L. Vinh, H. Nghiem, L.Vien, N. Cuong
• S13-P4 Measurements of Composition and Rates of Gas Generated in an Aqueous Homogeneous Reactor
  S. Chemerisov, A. Guelis, A. Bakel, and G. Vandegrift
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 143KB]
• S13-P5 Sorbent Selection for Mo-99 Recovery from Irradiated Aqueous Homogeneous Reactor Fuel Solutions
  D. Stepinski, A. Ziegler, J. Jerden, J. Fortner, K. Quigley, C. Mertz, A. Guelis, S. Chemerisov, A. Bakel and G. Vandegrift
• S13-P6 RoMol-99 – An Innovative Small-Scale LEU-Based Mo-99 Production Process 
  G-J. Beyer, R. Muenze, D. Novotny, M. Ahmad, M. Jehangir
• S13-P7 Optimization and Scale-up of a Nitric Acid Dissolver System for LEU-Foil Targets for Mo-99 Production
  J. Jerden Jr., A. Hebden, A. Bakel and G. Vandegrift
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 223KB]
• S13-P8 LEU Fuel Burnable Absorber Evaluation and Recommendations
  T. Totev
• S13-P9 The Role of HEU Minimization in Furthering Nonproliferation and Disarmament
  C. Hansell
• S13-P10 Safety Analysis for the First Loading of LEU Fuel into the WWR-M Research Reactor in Ukraine
  Y. Mahlers
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 228KB]
• S13-P12 New Friction Factor Correlation for the MIT Reactor Fuel Elements
  S. Wong, L-W. Hu , M. Kazimi
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 178KB]
• S13-P13 Flow-Induced Deformation of Foil-Based Fuel Plates
  G. Solbrekken, J. Kennedy
• S13-P14 Program for Domestic Production of Mo-99 in the United States
  G. Dale, J. Ireland, N. Pope
• S13-P15 Comparison of Pressure Drop Measurements and Calculations for HEU and LEU Fuel Assemblies for MARIA Reactor
  P. Garner, N. Hanan, W. Mieleszczenko
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 135KB]
• S13-P16 Effects of Fuel Plate and Assembly Position Tolerances on Steady-State Thermal Performance of the University of Missouri Research Reactor (MURR) LEU Core
  E.Feldman, B. Dionne, J.Stevens, J. Stillman
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 247KB]

Fuel Performance

• S14-P1 Microstructure of RERTR DU-Alloys Irradiated with Krypton Ions 
  J. Gan, D. Keiser, D. Wachs, B. Miller, T. Allen, M. Kirk, J. Rest
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 266KB]
• S14-P2 Transmission Electron Microscopy Investigation of Irradiated Atomised and Ground U(MO) Dispersion Fuel, With or Without Si Added to the Matrix
  W. Van Renterghem, A. Leenaers, S. Van Den Berghe, M.-C. Anselmet, F. Charollais, P. Lemoine, W. Petry
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 2.1MB]
• S14-P3 SEM Characterization of an Irradiated Dispersion Fuel Plate with U-10 Mo Particles and 6061 AL Matrix
  D. Keiser, J. Jue, A. Robinson, P. Medvedev, M. Finlay
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 2.2MB]
• S14-P4 Microstructural Analysis of Ground UMo Fuel With and Without Si Added to the Matrix, Irradiated to High Burn Up
  A. Leenaers, S. Van de Berghe, F. Charollais, P. Lemoine, C. Jarousse, A. Röhrmoser, W. Petry
• S14-P5 Optimization of the Si Content in UMo-Al(Si) Fuel Plates
  R. Jungwirth, H. Breitkreutz, W. Petry, A. Röhrmoser, W. Schmid, H. Palancher, C. Bertrand-Drira, C. Sabathier, X. Iltis, N. Tarisien, C. Jarousse
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 931KB]
• S14-P6 In-Situ High Temperature Neutron Diffraction Study of Phase Evolution in U-7Wt.% Mo/Al and U-7Wt.% Mo/Al-5Wt.% Si Fuel Rods
  J.Yang, H. Ryu and J. Park
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 731KB]
• S16-P1 Calculation of Uranium Molybdenum Dispersion Fuel Swelling by Matrix Creep Method
  X. Liu, T.iecheng Lu,  Z. Xing,  D. Qian, Y. Deng, Y. Liu
• S16-P2 Analysis of Fission Gas Bubbles and Microstructures of Irradiated U-Mo Fuel
  Y-S. Kim, G. Hofman, J. Rest, Y-S. Choo, A. Robinson
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 2.5MB]
• S16-P3 MTR Plates 3D Mechanical Modeling with MAIA
  V. Marelle, J.M. Gatt
• S16-P4 Effect of In-Pile Degredation of Thermal Conductivity on the Maxiumum Temperature of the Plate-Type U-Mo Dispersion Fuels
  P. Medvedev
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 57KB]
• S16-P5 Kinetics of the Interaction Layer Formation Between Gamma-UMo and Aluminum by Thermal and Gravimetric Analysis
  F. Oliveira, E. Carvalho, H. Riella

Safety Analysis

• S15-P1 HEU/LEU Conversion of TRIGA Reactors
  A. Veca, J. Bolin, C. Ellis, J. Crozier, L. Halle
• S15-P2 Oregon State TRIGA Reactor Conversion Analysis Highlights
  S. Keller, W. Marcum, B. Woods, S. Reese, T. Palmer, M. Hartman, J. Matos, J. Stevens, F. Dunn, E. Feldman 
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 259KB]
• S15-P3 Loss of Coolant Analysis for the Oregon State University Triga Reactor
  F.E. Dunn, J.E. Matos
• S15-P4 Analysis of a Hypothetical Partial Loss-of-Coolant Accident in the University of Wisconsin TRIGA-Fueled Research Reactor
  E. Feldman, T. Sofu, J. Matos
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 137KB]
• S15-P5 Evaluation of the Thermal-Hydraulics Operating Limits of the HEU-LEU Transition Cores for the MITR
  Y. Wang, L-W. Hu  
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 332KB]

Conversion Analysis and Methods

• S17-P1 IRT-SOFIA Conversion Feasilbility Study
  T. Apostolov, S. Belousov, N. Hanan, J. Matos
• S17-P2 CERCA Fuel Assembly Testing in MARIA Reactor-Safety Analysis Summary and Testing Program Scope
  K. Pytel, W. Mieleszczenko, J. Lechniak, A. Mołdysz, K. Andrzejewski, T. Kulikowska, Z. Marcinkowska, P. Garner, N. Hanan 
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 387KB]
• S17-P3 Conversion of WWR-SM Reactor INP AS Republic of Uzbekistan
  U. Salikhbaev, A. Dosimbaev, S. Baytelesov, F. Kungurov
• S17-P4 Implementation and Verification of Mishima's CHF Data at Low Flow and Atmoshperic Pressure in the PLTEMP/ANL Code
  M. Kalimullah, E. Feldman, and A. Olson
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 158KB]
• S17-P5 Detailed BR2 Steady-State and Decay Power Distributions  During 1963 A/400/1 Flow Test
  B. Dionne, C. Tzanos, J. Matos
  Posted on: Mon, Jun. 18, 2012  | [ PDF, 593KB]
• S17-P6 Application of PARET/V7.5 for the Transient Analysis of the BR2 Reactor: Reactivity Insertion Transients with Automatic Power Reduction by the Control Rods
  S. Kalcheva, E. Koonen, A. Olson, J. Matos
• S17-P7 Characteristics of the WWR-K Test Core and  the LEU LTAs to be Placed in the Central Experimental Beryllium Device
  F. Аrinkin, P. Chakrov, L. Chekushina, Sh. Gizatulin, S. Koltochnik, N. Hanan and P. Garner
  Posted on: Mon, Oct. 10, 2011  | [ PDF, 158KB]