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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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Accelerator-Driven Subcritical Target Concept for Transmutation of Nuclear Wastes
Gregory J. Van Tuyle, Michael Todosow, Marcia J. Geiger, Arnold L. Aronson, H. Takahashi
Nuclear Technology | Volume 101 | Number 1 | January 1993 | Pages 1-17
Technical Paper | Waste Management Special / Enrichment and Reprocessing System | doi.org/10.13182/NT93-A34764
Risk, Uncertainty in Risk, and the EPA Release Limits for Radioactive Waste Disposal
Jon C. Helton
Nuclear Technology | Volume 101 | Number 1 | January 1993 | Pages 18-39
Technical Paper | Waste Management Special / Radioactive Waste Disposal | doi.org/10.13182/NT93-A34765
An Ocean Island Geological Repository—A Second-Generation Option for Disposal of Spent Fuel and High-Level Waste
Charles W. Forsberg
Nuclear Technology | Volume 101 | Number 1 | January 1993 | Pages 40-53
Technical Paper | Waste Management Special / Radioactive Waste Disposal | doi.org/10.13182/NT93-A34766
A Numerical Study of Transient Mass Transport Through a Circular Hole Connecting Two Semi-Infinite Media
David W. DePaoli, Timothy C. Scott
Nuclear Technology | Volume 101 | Number 1 | January 1993 | Pages 54-66
Technical Paper | Waste Management Special / Radioactive Waste Disposal | doi.org/10.13182/NT93-A34767
An Analytical Model for Radionuclide Transport in a Single Fracture: Considering Nonequilibrium Matrix Sorption
Ching-Hor Lee, Shi-Ping Teng
Nuclear Technology | Volume 101 | Number 1 | January 1993 | Pages 67-78
Technical Paper | Waste Management Special / Radioactive Waste Disposal | doi.org/10.13182/NT93-A34768
Diffusion of the 241Am → 237Np Decay Chain Limited by Their Elemental Solubilities in the Artificial Barriers of High-Level Radioactive Waste Repositories
Joonhong Ahn, Atsuyuki Suzuki
Nuclear Technology | Volume 101 | Number 1 | January 1993 | Pages 79-91
Technical Paper | Waste Management Special / Radioactive Waste Disposal | doi.org/10.13182/NT93-A34769
Migration of Radionuclides in Fractured Porous Rock: Analytical Solution for a Flux-Type Boundary Condition
Shean-Lang Chiou, Shih-Hai Li
Nuclear Technology | Volume 101 | Number 1 | January 1993 | Pages 92-100
Technical Paper | Waste Management Special / Radioactive Waste Disposal | doi.org/10.13182/NT93-A34770
A Methodology for the Design and Analysis of a Sensor Failure Detection Network
H. P. Chou, J. N. Ning, T. M. Tsai
Nuclear Technology | Volume 101 | Number 1 | January 1993 | Pages 101-109
Technical Note | Waste Management Special / Reactor Operation | doi.org/10.13182/NT93-A34771
Neural Network Model for Estimating Departure from Nucleate Boiling Performance of a Pressurized Water Reactor Core
Hyun-Koon Kim, Seung-Hyuk Lee, Soon-Heung Chang
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 111-122
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34773
Radis—a Regional Nuclear Accident Consequence Analysis Model for Hong Kong
Mankit Ray Yeung, Eric M. K. Ching
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 123-139
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34774
A Comparative Study of Nuclear Accident Consequences for Hong Kong
Eric M. K. Ching, Mankit Ray Yeung
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 140-148
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34775
A Probabilistic Safety Criterion for Core Melt Frequency Based on the Distribution of the Public’s Safety Goals
Ki-Yong Ra, Byong-Whi Lee, Soon-Heung Chang
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 149-158
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34776
Abnormal Event Identification in Nuclear Power Plants Using a Neural Network and Knowledge Processing
Yukiharu Ohga, Hiroshi Seki
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 159-167
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34777
The Use of Nonlinear Regression Analysis for Integrating Pollutant Concentration Measurements with Atmospheric Dispersion Modeling for Source Term Estimation
Leslie L. Edwards, Robert P. Freis, Linda G. Peters, Paul H. Gudiksen, Sergei E. Pitovranov
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 168-180
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34778
RELAP5 Modeling of the Westinghouse Model D4 Steam Generator
Borut Mavko, Stojan Petelin, Oton Gortnar
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 181-192
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34779
Some Aspects of Nuclear Power Plant Safety Under War Conditions
Andrej Stritar, Borut Mavko, Janez Sušnik, Božidar Šarler
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 193-201
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34780
A Power-Rate-Dependent Model for Pellet/Cladding Mechanical Interaction
Chlng-Kong Chao, Che-Chung Tseng
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 202-211
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34781
An Application of the Concept of Limit of Expenditures in Risk Reduction Measures to the Brazilian Case
L. F. Oliveira, J. E. Lima, P. F. Frutuoso E Melo
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 212-217
Technical Paper | Economic | doi.org/10.13182/NT93-A34782
Fire Behavior and Filter Plugging During a Postulated Solvent Fire in the Extraction Process of a Nuclear Fuel Reprocessing Plant
Kazuichiro Hashimoto, Gunji Nishio, Kunihisa Soda
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 218-226
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT93-A34783
A Two-Fluid Two-Phase Model for Thermal-Hydraulic Analysis of a U-Tube Steam Generator
Huan-Jen Hung, Ching-Chang Chieng, Bau-Shei Pei, Song-Feng Wang
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 227-236
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT93-A34784
Transport Analysis of Several Cross-Section Libraries Used for Reactor Pressure Vessel Fluence Calculations
Alireza Haghighat, Ramana Veerasingam
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 237-243
Technical Note | Material | doi.org/10.13182/NT93-A34785
RELAP5/MOD3 Simulation of the Water Cannon Phenomenon
W. S. Yeung, Jen Wu, R. T. Fernandez, R. K. Sundaram
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 244-251
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT93-A34786
Results of Recent Investigations at Sandia National Laboratories on Core Debris Interactions with Concrete
Dana A. Powers, Ervin R. Copus, David R. Bradley
Nuclear Technology | Volume 101 | Number 3 | March 1993 | Pages 255-261
Technical Paper | Severe Accident Technology / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34788
Fission Product Transport Behavior
T. S. Kress, E. C. Beahm, C. F. Weber, G. W. Parker
Nuclear Technology | Volume 101 | Number 3 | March 1993 | Pages 262-269
Technical Paper | Severe Accident Technology / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34789
Fission Product Release from Fuel Under Severe Accident Conditions
Richard R. Hobbins, David A. Petti, Donald L. Hagrman
Nuclear Technology | Volume 101 | Number 3 | March 1993 | Pages 270-281
Technical Paper | Severe Accident Technology / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34790
Recent Advances in Severe Accident Technology — Direct Containment Heating in Advanced Light Water Reactors
Mario H. Fontana
Nuclear Technology | Volume 101 | Number 3 | March 1993 | Pages 282-298
Technical Paper | Severe Accident Technology / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34791
The Probability of Liner Failure in a Mark-I Containment, Part I: Probabilistic Framework and Results
Theo G. Theofanous, Hongfei Yan, Farouk Eltawila
Nuclear Technology | Volume 101 | Number 3 | March 1993 | Pages 299-331
Technical Paper | Severe Accident Technology / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34792
The Probability of Liner Failure in a Mark-I Containment, Part II: Melt Release and Spreading Phenomena
Theo G. Theofanous, Hongfei Yan
Nuclear Technology | Volume 101 | Number 3 | March 1993 | Pages 332-353
Technical Paper | Severe Accident Technology / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34793
The Probability of Liner Failure in a Mark-I Containment, Part III: Corium/Concrete Interactions and Liner Attack Phenomena
W. H. Amarasooriya, Hongfei Yan, Umesh Ratnam,†, Theo G. Theofanous
Nuclear Technology | Volume 101 | Number 3 | March 1993 | Pages 354-384
Technical Paper | Severe Accident Technology / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34794
Cooling of Core Debris Within the Reactor Vessel Lower Head
Robert E. Henry, James P. Burelbach, Robert J. Hammersley, Christopher E. Henry, George T. Klopp
Nuclear Technology | Volume 101 | Number 3 | March 1993 | Pages 385-399
Technical Paper | Severe Accident Technology / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34795
Hydrogen Production and Combustion in Severe Reactor Accidents: An Integral Assessment Perspective
Martin G. Plys
Nuclear Technology | Volume 101 | Number 3 | March 1993 | Pages 400-410
Technical Paper | Severe Accident Technology / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34796
