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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
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Aging Tests of Neutron-Shielding Materials for Transport of Storage Casks
Herve Issard, Pascale Abadie
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 2-8
Special Issue Technical Paper | Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Materials for Nuclear Systems | doi.org/10.13182/NT11-A12538
Accelerated Testing of Neutron-Absorbing Alloys for Nuclear Criticality Control
R. E. Mizia, T. E. Lister
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 9-21
Special Issue Technical Paper | Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Materials for Nuclear Systems | doi.org/10.13182/NT11-A12539
Combined Experimental and Computational Approach to Predict the Glass-Water Reaction
E. M. Pierce, D. H. Bacon
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 22-39
Special Issue Technical Paper | Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A12540
Feasibility of Reduced Boron Concentration Operation in Pressurized Water Reactor Plants
Aung Tharn Daing, Myung-Hyun Kim
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 40-56
Technical Paper | Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Fission Reactors | doi.org/10.13182/NT176-40
Flashing-Induced Instability Analysis and the Start-Up of Natural Circulation Boiling Water Reactors
Rui Hu, Mujid S. Kazimi
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 57-71
Technical Paper | Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Fission Reactors | doi.org/10.13182/NT11-A12542
Automatic Boiling Water Reactor Control Rod Pattern Design Using Ant Colony Optimization Algorithm
Cheng-Der Wang, Chaung Lin
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 72-82
Technical Paper | Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Fission Reactors | doi.org/10.13182/NT11-A12543
Experimental Study on the Behavior of Suspended Aerosols of Sodium and Nonradioactive Fission Products (SrO2 and CeO2) in a Closed Vessel
V. Subramanian, R. Baskaran, J. Misra, R. Indira
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 83-92
Reactor Safety | doi.org/10.13182/NT11-A12544
Analysis of the BR2 Loss-of-Flow Test A
Constantine P. Tzanos, B. Dionne
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 93-105
Thermal Hydraulics | doi.org/10.13182/NT11-A12545
Using the Levenberg-Marquardt Method for Solutions of Inverse Transport Problems in One- and Two-Dimensional Geometries
Keith C. Bledsoe, Jeffrey A. Favorite, Tunc Aldemir
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 106-126
Radiation Transport and Protection | doi.org/10.13182/NT176-106
High-Performance Differential Pressure Monitoring Devices Using Pulsating Sensors for a Sodium-Cooled Fast Breeder Reactor
K. Praveen, M. P. Rajiniganth, A. D. Arun, R. Ananthanarayanan, N. Malathi, P. Sahoo, N. Murali
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 127-137
Nuclear Plant Operations and Control | doi.org/10.13182/NT11-A12547
Yucca Mountain Waste Package Closure System Robotic Welding and Inspection System
C. I. Nichol, D. P. Pace, E. D. Larsen, T. R. McJunkin, D. E. Clark, M. L. Clark, K. L. Skinner, A. D. Watkins, H. B. Smartt
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 138-146
Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A12548
Hot-Test Results of the Advanced Spent Fuel Conditioning Process Safeguards Neutron Counter for PWR Spent Fuel Rods
Tae-Hoon Lee, Young Soo Kim, Hee-Sung Shin, Ho-Dong Kim
Nuclear Technology | Volume 176 | Number 1 | October 2011 | Pages 147-154
Radiation Measurements and General Instrumentation | doi.org/10.13182/NT11-A12549
Review Paper: Review of Instrumentation for Irradiation Testing of Nuclear Fuels and Materials
Bong Goo Kim, Joy L. Rempe, Jean-François Villard, Steinar Solstad
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 155-187
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT11-A13294
Burnup Performance of Sodium-Cooled Fast Reactor by Utilizing Thorium-Based Fuels
Shadi Z. Ghrayeb, Kostadin N. Ivanov, Samuel H. Levine, Eric P. Loewen
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 188-194
Technical Paper | Fission Reactors | doi.org/10.13182/NT11-A13295
Development of Effective Algorithm for Coupled Thermal-Hydraulic-Neutron-Kinetics Analysis of Reactivity Transient
Joanna Peltonen, Tomasz Kozlowski
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 195-210
Technical Paper | Reactor Safety | doi.org/10.13182/NT11-A13296
Measurements of Aerosol Charge and Size Distribution for Graphite, Gold, Palladium, and Silver Nanoparticles
Matthew P. Simones, Veera R. Gutti, Ryan M. Meyer, Sudarshan K. Loyalka
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 211-226
Technical Paper | Reactor Safety | doi.org/10.13182/NT10-10
Uranium Price Versus Cumulative Use
Clifford E. Singer, Hermann von Brevern
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 227-237
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT11-A13298
Computational Fluid Dynamics Analysis of Very High Temperature Gas-Cooled Reactor Cavity Cooling System
Angelo Frisani, Yassin A. Hassan, Victor M. Ugaz
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 238-259
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT11-A13299
Assessment of MARS Code for Predicting Critical Heat Flux Under Heaving Conditions
Jin-Seok Hwang, Jong-Won Kim, Heon-Uk Nam, Goon-Cherl Park
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 260-273
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT11-A13300
A C5 Benchmark Problem with the Discrete Ordinates Radiation Transport Code Denovo
G. Yesilyurt, K. T. Clarno, T. M. Evans, G. G. Davidson, P. B. Fox
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 274-283
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT11-A13301
Control Rod Drop Surveillance Using Two Friction Coefficients
J. Blázquez, I. Vallejo, A. García-Berrocal, M. Balbás
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 284-289
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT11-A13302
Separation of Transmutation- and Fission-Produced Radioisotopes from Irradiated Beryllium
Troy J. Tranter, Richard D. Tillotson, Nick R. Mann, Glen R. Longhurst
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 290-295
Technical Paper | Decontamination/ Decommissioning | doi.org/10.13182/NT11-A13303
A Fruit of Yucca Mountain: The Remote Waste Package Closure System
Kevin Skinner, Greg Housley, Colleen Shelton-Davis
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 296-308
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT11-A13304
Measurement of Tritium During Voloxidation of Zircaloy-2 Cladding
Mark L. Crowder, James E. Laurinat, John A. Stillman
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Pages 309-313
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT11-A13305
Corrigendum
Nuclear Technology | Volume 176 | Number 2 | November 2011 | Page 314
doi.org/10.13182/NT11-A13306
Neutronic Design and Analysis of a Small Nuclear Reactor to Supply District Heating and Electrical Energy to Canadian Forces Bases Located in the Arctic or the Northern Remote Communities
Stéphane Paquette, Hugues W. Bonin
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 315-336
Technical Paper | Fission Reactors | doi.org/10.13182/NT11-A13311
Thermoeconomic Analysis of High-Temperature Gas-Cooled Reactors with Steam Methane Reforming for Hydrogen Production
Duk Jin Kim, Jong Hyun Kim, K. F. Barry, Ho-Young Kwak
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 337-351
Technical Paper | Fission Reactors | doi.org/10.13182/NT11-A13312
Analyses of the Phébus FPT3 Experiment Using the Severe Accident Codes ATHLET-CD, ICARE/CATHARE, and MELCOR
Georges Repetto, Olivier de Luze, Tilman Drath, Marco K. Koch, Thorsten Hollands, Klaus Trambauer, Christine Bals, Henrique Austregesilo, Jon Birchley
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 352-371
Technical Paper | Reactor Safety | doi.org/10.13182/NT11-A13313
Triggered Steam Explosions with the Corium Melts of Various Compositions in a Two-Dimensional Interaction Vessel in the TROI Facility
J. H. Kim, B. T. Min, I. K. Park, S. W. Hong
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 372-386
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT11-A13314
Neutron Channeling Through Neutron Absorber Sheets
Alan H. Wells, Albert J. Machiels
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 387-394
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT11-A13315
Use of Multiple Layers of Repeating Material to Effectively Collimate an Isotropic Neutron Source
Z. D. Whetstone, K. J. Kearfott
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 395-413
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT10-118
Advanced Cable-Testing Techniques for Nuclear Power Plants
Hashem M. Hashemian, Wendell C. Bean
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 414-429
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT11-A13317
Managing Beryllium in Nuclear Facility Applications
G. R. Longhurst, K. Tsuchiya, C. H. Dorn, S. L. Folkman, T. H. Fronk, M. Ishihara, H. Kawamura, T. N. Tranter, R. Rohe, M. Uchida, E. Vidal
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 430-441
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT11-A13318
Evolution of the Leak-Before-Break Concept in Nuclear Plants: Issues and Resolutions in the Process of Regulatory Actions
Mir Sajjad Ali
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 442-451
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT11-A13319
Laboratory Tests of an Ultrasonic Inspection Technique to Identify Defective CANDU Fuel Elements
W. H. Huang, T. W. Krause, B. J. Lewis
Nuclear Technology | Volume 176 | Number 3 | December 2011 | Pages 452-461
Technical Note | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT11-A13320
