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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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Thermal-Hydraulic Design of the Accelerator Production of Tritium Tungsten Neutron Source
Kemal O. Pasamehmetoglu, Gordon J. Willcutt, Jr., Jay S. Elson, Donald A. Siebe
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 3-14
Technical Paper | Accelerator Applications | doi.org/10.13182/NT00-A3125
Disposition of Nuclear Waste Using Subcritical Accelerator-Driven Systems: Technology Choices and Implementation Scenarios
Francesco Venneri, Mark A. Williamson, Ning Li, Michael G. Houts, Richard A. Morley, Denis E. Beller, William Sailor, George Lawrence
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 15-29
Technical Paper | Accelerator Applications | doi.org/10.13182/NT00-A3126
Nuclear Simulation and Radiation Physics Investigations of the Target Station of the European Spallation Neutron Source
Detlef Filges, Ralf-Dieter Neef, Hartwig Schaal
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 30-48
Technical Paper | Accelerator Applications | doi.org/10.13182/NT00-A3127
Target Systems Overview for the Spallation Neutron Source
Tony A. Gabriel, John M. Barnes, Lowell A. Charlton, James DiStefano, Ken Farrell, John Haines, Jeffrey O. Johnson, Louis K. Mansur, Steve J. Pawel, Moshe Siman-Tov, Rusi Taleyarkhan, Mark W. Wendel, Thomas J. McManamy, Mark J. Rennich
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 49-60
Technical Paper | Accelerator Applications | doi.org/10.13182/NT00-A3128
Intensity and Spectra of a White Light Neutron Source Produced by a 70-MeV Proton Accelerator
Qing Biao Shen
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 61-65
Technical Paper | Accelerator Applications | doi.org/10.13182/NT00-A3129
Once-Through Thermal-Spectrum Accelerator-Driven Light Water Reactor Waste Destruction Without Reprocessing
Charles D. Bowman
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 66-93
Technical Paper | Accelerator Applications | doi.org/10.13182/NT00-1
Neutronic Design Studies for the Spallation Neutron Source
Lowell A. Charlton, John M. Barnes, Jeffrey O. Johnson, Tony A. Gabriel
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 94-102
Technical Paper | Accelerator Applications | doi.org/10.13182/NT00-A3131
The Accelerator Production of Tritium Materials Test Program
Stuart A. Maloy, Walter F. Sommer, Michael R. James, Tobias J. Romero, Manuel R. Lopez, Eugene Zimmermann, James M. Ledbetter
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 103-114
Technical Paper | Accelerator Applications | doi.org/10.13182/NT00-A3132
Target/Blanket Design for the Accelerator Production of Tritium Plant
Michael W. Cappiello, Paul W. Lisowski
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 115-127
Technical Paper | Accelerator Applications | doi.org/10.13182/NT00-A3133
Benchmark Calculations for Standard and DUPIC CANDU Fuel Lattices Compared with the MCNP-4B Code
Gyuhong Roh, Hangbok Choi
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 128-151
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3134
Mitigation Measures Following a Loss-of-Residual-Heat-Removal Event During Shutdown
Kwang Won Seul, Young Seok Bang, Hho Jung Kim
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 152-166
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3135
Analysis of an Advanced Test Reactor Small-Break Loss-of-Coolant Accident with an Engineered Safety Feature to Automatically Trip the Primary Coolant Pumps
Steven T. Polkinghorne, Cliff B. Davis, Richard T. McCracken
Nuclear Technology | Volume 132 | Number 1 | October 2000 | Pages 167-178
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3136
Conceptual Design of a Clinical BNCT Beam in an Adjacent Dry Cell of the Jozef Stefan Institute TRIGA Reactor
Marko Maucec
Nuclear Technology | Volume 132 | Number 2 | November 2000 | Pages 179-195
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3137
Analysis of Kuosheng Station Blackout Accident Using MELCOR 1.8.4
Shih-Jen Wang, Chien-Sheng Chien, Te-Chuan Wang, Kwang-Sheng Chiang
Nuclear Technology | Volume 132 | Number 2 | November 2000 | Pages 196-205
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3138
Comparison of CECOR Algorithm to Lagrange Multiplier Method to Estimate Reactor Power Distributions
Raymond J. Webb, James C. Brittingham
Nuclear Technology | Volume 132 | Number 2 | November 2000 | Pages 206-213
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3139
A Pressurized Water Reactor Plutonium Incinerator Based on Thorium Fuel and Seed-Blanket Assembly Geometry
A. Galperin, M. Segev, M. Todosow
Nuclear Technology | Volume 132 | Number 2 | November 2000 | Pages 214-226
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3140
Analysis of Main-Steam-Line-Break Accidents Using RETRAN-3D for Pressurized Thermal Shock Evaluation of the Kori Nuclear Unit-1 Power Plant
Jae-Hak Kim, Soon-Joon Hong, Goon-Cherl Park, Yong-Soo Kim
Nuclear Technology | Volume 132 | Number 2 | November 2000 | Pages 227-239
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3141
Constant-Temperature Calorimetry for In-Core Power Measurement
Thomas D. Radcliff, Don W. Miller, Andrew C. Kauffman
Nuclear Technology | Volume 132 | Number 2 | November 2000 | Pages 240-255
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3142
The Effect of Accident Conditions on the Molten Core Material Relocation into the Lower Head of a PWR Vessel with Application to TMI-2
Xuegao An, Vijay K. Dhir, David Okrent
Nuclear Technology | Volume 132 | Number 2 | November 2000 | Pages 256-280
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3143
Analyses and Development of Effective Compensation Shields in a Multilegged Duct Streaming System
Kohtaro Ueki, Masayoshi Kawai
Nuclear Technology | Volume 132 | Number 2 | November 2000 | Pages 281-289
Technical Paper | Radiation Protection | doi.org/10.13182/NT00-A3144
Application of Radio-Frequency Plasma Glow Discharge to Removal of Uranium Dioxide from Metal Surfaces
Mohamed S. El-Genk, Hamed H. Saber
Nuclear Technology | Volume 132 | Number 2 | November 2000 | Pages 290-308
Technical Paper | Decontamination/Decommissioning | doi.org/10.13182/NT00-A3145
Design and Characteristics of the JRR-3M Thermal Neutron Radiography Facility and Its Imaging Systems
Masahito Matsubayashi, Hisao Kobayashi, Takashi Hibiki, Kaichiro Mishima
Nuclear Technology | Volume 132 | Number 2 | November 2000 | Pages 309-324
Technical Paper | Radioisotopes | doi.org/10.13182/NT00-A3146
TRIGA Mark II Criticality Benchmark Experiment with Burned Fuel
Andreja Persic, Matjaz Ravnik, Tomaz Zagar
Nuclear Technology | Volume 132 | Number 3 | December 2000 | Pages 325-338
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3147
A Model for Calculating the Accident Washout Factor for a Coastal Nuclear Power Plant Site
Erbang Hu, Rentai Yao, Zhanrong Gao, Shuxian Wang, Gang Jiang, Jia Yi Chen
Nuclear Technology | Volume 132 | Number 3 | December 2000 | Pages 339-351
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3148
Optimization of the Surveillance Test Interval of the Safety Systems at the Plant Level
Joon-Eon Yang, Tae-Yong Sung, Youngho Jin
Nuclear Technology | Volume 132 | Number 3 | December 2000 | Pages 352-365
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3149
The Effect of Measurement Bias on Nuclear Criticality Safety Calculations for WIPP TRUPACT-II Shipments
Larry G. Blackwood, Yale D. Harker
Nuclear Technology | Volume 132 | Number 3 | December 2000 | Pages 366-374
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3150
Direct-Contact Heat Transfer Model for Dispersed-Flow Film Boiling
Stephen M. Bajorek, Michael Y. Young
Nuclear Technology | Volume 132 | Number 3 | December 2000 | Pages 375-388
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3151
Neurocontrol of Pressurized Water Reactors in Load-Follow Operations
Chaung Lin, Chih-Ming Shen
Nuclear Technology | Volume 132 | Number 3 | December 2000 | Pages 389-402
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT00-4
Dynamic Rod Worth Measurement
Y. A. Chao, D. M. Chapman, D. J. Hill, L. R. Grobmyer
Nuclear Technology | Volume 132 | Number 3 | December 2000 | Pages 403-412
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT00-A3153
Studies on the Separation of Minor Actinides from High-Level Wastes by Extraction Chromatography Using Novel Silica-Based Extraction Resins
Yuezhou Wei, Mikio Kumagai, Yoichi Takashima, Giuseppe Modolo, Reinhard Odoj
Nuclear Technology | Volume 132 | Number 3 | December 2000 | Pages 413-423
Technical Paper | Reprocessing | doi.org/10.13182/NT00-A3154
Efficient Simulation Modeling of an Integrated High-Level-Waste Processing Complex
Michael V. Gregory, Pran K. Paul
Nuclear Technology | Volume 132 | Number 3 | December 2000 | Pages 424-435
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3155
