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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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Integration of Neural Networks with Fuzzy Reasoning for Measuring Operational Parameters in a Nuclear Reactor
Andreas Ikonomopoulos, Lefteri H. Tsoukalas, Robert E. Uhrig
Nuclear Technology | Volume 104 | Number 1 | October 1993 | Pages 1-12
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34866
Sensitivity and Uncertainty Analysis of Accident Management Strategies Involving Multiple Decisions
Moosung Jae, Antony D. Milici, William E. Kastenberg, George E. Apostolakis
Nuclear Technology | Volume 104 | Number 1 | October 1993 | Pages 13-36
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34867
Constituent Migration Model for U-Pu-Zr Metallic Fast Reactor Fuel
Masayoshi Ishida, Takanari Ogata, Motoyasu Kinoshita
Nuclear Technology | Volume 104 | Number 1 | October 1993 | Pages 37-51
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34868
Postirradiation Recovery of a Reactor Pressure Vessel Steel Investigated by Positron Annihilation and Microhardness Measurements
Ramiro Pareja, Nieves De Diego, Rosa Maria De La Cruz, Javier Del Río
Nuclear Technology | Volume 104 | Number 1 | October 1993 | Pages 52-63
Technical Paper | Material | doi.org/10.13182/NT93-A34869
A New Flooding Correlation Development and Its Critical Heat Flux Predictions Under Low Air-Water Flow Conditions in Savannah River Site Assembly Channels
Si Y. Lee
Nuclear Technology | Volume 104 | Number 1 | October 1993 | Pages 64-75
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT93-A34870
Analysis of Experiments for Steam Condensation in the Presence of Non-condensable Gases Using the RELAP5/MOD3 Code
Yassin A. Hassan, Laxminarayan L. Raja
Nuclear Technology | Volume 104 | Number 1 | October 1993 | Pages 76-88
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT93-A34871
Ventilation Rates by Measurement of Induced Radon Time-Dependent Behavior—Theory, Application, and Evaluation
Bobby E. Leonard
Nuclear Technology | Volume 104 | Number 1 | October 1993 | Pages 89-105
Technical Paper | Radiation Protection | doi.org/10.13182/NT93-A34872
Development of an In-Service Inspection Technique for the Intermediate Heat Exchanger Tubes of the High-Temperature Engineering Test Reactor
Yoshiyuki Inagaki, Yoshiaki Miyamoto, Tamao Nakajima, Tsuyoshi Kozuma, Hajime Shoji
Nuclear Technology | Volume 104 | Number 1 | October 1993 | Pages 106-117
Technical Paper | Reactor Operation | doi.org/10.13182/NT93-A34873
An Assessment of Liquid-Metal Centrifugal Pumps at Three Fast Reactors
Mark S. Smith, Darren H. Wood, James D. Drischler
Nuclear Technology | Volume 104 | Number 1 | October 1993 | Pages 118-127
Technical Paper | Reactor Operation | doi.org/10.13182/NT93-A34874
Detection of Small Leakages by a Combination of Dedicated Kalman Filters and an Extended Version of the Binary Sequential Probability Ratio Test
Attila Rácz
Nuclear Technology | Volume 104 | Number 1 | October 1993 | Pages 128-146
Technical Paper | Reactor Control | doi.org/10.13182/NT93-A34875
Control System Modification in the Taiwan Research Reactor
Shih-Jen Wang, Min-Song Lin
Nuclear Technology | Volume 104 | Number 1 | October 1993 | Pages 147-153
Technical Note | Reactor Operation | doi.org/10.13182/NT93-A34876
Validation of the TEXSAN Thermal-Hydraulic Analysis Program
Shawn P. Burns, Dale E. Klein
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 157-163
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34879
The Influence of Moisture on Air Oxidation of UO2: Calculations and Observations
Peter Taylor, Robert J. Lemire, Donald D. Wood
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 164-170
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34880
An Evaluation of the Use of Depleted Uranium as a Structural Component for Transport Casks
Paul McConnell, Richard Salzbrenner, Gerald W. Wellman, Ken B. Sorenson
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 171-181
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34881
Demands Placed on Waste Package Performance Testing and Modeling by Some General Results of Reliability Analysis
Dwayne A. Chesnut
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 182-192
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34882
Long-Term Comparison of Dissolution Behavior Between Fully Radioactive and Simulated Nuclear Waste Glasses
Xiangdong Feng, John K. Bates, Edgar C. Buck, Charles R. Bradley, Meiling Gong
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 193-206
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34883
Criticality Safety of Transuranic Storage Arrays at the Waste Isolation Pilot Plant
William A. Boyd, Mark W. Fecteau
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 207-218
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34884
Multibarrier Copper-Base Containers for High-Level Waste Disposal
Dale T. Peters, Konrad J. A. Kundig, David F. Medley, Paul A. Enders
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 219-232
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34885
Attainment of Radiation Equivalency in Nuclear Power Radioactive Product Management
E. O. Adamov, I. Kh. Ganev, V. V. Orlov
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 233-240
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34886
Combined Natural Convection and Surface Radiation in the Annular Region Between a Volumetrically Heated Inner Tube and a Finite Conducting Outer Tube
Steven Gianoulakis, Dale E. Klein
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 241-251
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34887
Geochemical Modeling of a Bentonite-Groundwater-Rock System in the Presence of Uranium
Iréne Lundén, Karin Andersson
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 252-257
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34888
Radionuclide Migration in Fractured Porous Rock: Analytical Solution for a Kinetic Solubility-Limited Dissolution Model
Shih-Hai Li, Shean-Lang Chiou
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 258-271
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34889
Sensitivity and Uncertainty Analyses Applied to One-Dimensional Radionuclide Transport in a Layered Fractured Rock. Part I: Analytical Solutions and Local Sensitivities
A. Berge Gureghian, Yih-Tsuen Wu, Budhi Sagar, Richard B. Codell
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 272-296
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34890
Sensitivity and Uncertainty Analyses Applied to One-Dimensional Radionuclide Transport in a Layered Fractured Rock. Part II: Probabilistic Methods Based on the Limit-State Approach
Yih-Tsuen Wu, A. Berge Gureghian, Budhi Sagar, Richard B. Codell
Nuclear Technology | Volume 104 | Number 2 | November 1993 | Pages 297-308
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34891
Differences in Oxidation Behavior of Used CANDU Fuel During Prolonged Storage in Moisture-Saturated Air and Dry Air at 150°C
Kenneth M. Wasywich, William H. Hocking, David W. Shoesmith, Peter Taylor
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 309-329
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34893
Hydrogen Generation During Treatment of Simulated High-Level Radioactive Waste with Formic Acid
James A. Ritter, John R. Zamecnik, Chia-Lin W. Hsu
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 330-342
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34894
Corrosion of High-Level Waste Packaging Materials in Disposal Relevant Brines
Emmanuel Smailos
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 343-350
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34895
Desorption Kinetics of Radionuclides Fixed in Cement Matrix
T. M. Krishnamoorthy, S. N. Joshi, G. R. Doshi, R. N. Nair
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 351-357
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34896
Thermal Loading Studies Using Cooling Enhancement and Ventilation
George Danko
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 358-371
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34897
A Comparison of Glass Reaction at High and Low Glass Surface/Solution Volume
William L. Ebert, John K. Bates
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 372-384
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34898
Implications of Episodic Nonequilibrium Fracture-Matrix Flow on Repository Performance
John J. Nitao, Thomas A. Buscheck, Dwayne A. Chesnut
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 385-402
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34899
Gamma Radiolysis of Water Solutions Relevant to the Nuclear Fuel Waste Management Program
S. Sunder, H. Christensen
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 403-417
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34900
Repository-Heat-Driven Hydrothermal Flow at Yucca Mountain, Part I: Modeling and Analysis
Thomas A. Buscheck, John J. Nitao
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 418-448
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34901
Repository-Heat-Driven Hydrothermal Flow at Yucca Mountain, Part II: Large-Scale In Situ Heater Tests
Thomas A. Buscheck, John J. Nitao, Dale G. Wilder
Nuclear Technology | Volume 104 | Number 3 | December 1993 | Pages 449-471
Technical Paper | Special Issue on Waste Management / Radioactive Waste Management | doi.org/10.13182/NT93-A34902
