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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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Reactivity Anomalies in the Fast Flux Test Facility—An Evaluation of Data from Cycles 1 Through 8
Bradley J. Knutson, Richard A. Harris
Nuclear Technology | Volume 89 | Number 1 | January 1990 | Pages 9-17
Technical Paper | Fission Reactor | doi.org/10.13182/NT90-A34355
A New Control Strategy for Nuclear Power Reactors
Hiroaki Wakabayashi, Nobuhiro Nakanishi, Kazunori Sasaki, Morikazu Takegaki
Nuclear Technology | Volume 89 | Number 1 | January 1990 | Pages 18-35
Technical Paper | Fission Reactor | doi.org/10.13182/NT90-A34356
Possibilities for Improvements in Liquid-Metal Reactors Using Liquid-Metal Magnetohydrodynamic Energy Conversion
Amitzur Z. Barak, Leif Blumenau, H. Branover, A. El-Boher, Ehud Greenspan, E. Spero, S. Sukoriansky
Nuclear Technology | Volume 89 | Number 1 | January 1990 | Pages 36-51
Technical Paper | Fission Reactor | doi.org/10.13182/NT90-A34357
A Limit Line for Earthquake Intensity Attenuation
Salvatore Taibi
Nuclear Technology | Volume 89 | Number 1 | January 1990 | Pages 52-55
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34358
Experimental and Numerical Investigations of Sodium Boiling Experiments in Pin Bundle Geometry
Maurizio Bottoni, Burkhardt Dorr, Christoph Homann, Franz Huber, Karl Mattes, F. W. Peppler, Dankward Struwe
Nuclear Technology | Volume 89 | Number 1 | January 1990 | Pages 56-82
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34359
A New Safety Approach in the Design of Fast Reactors
Robert J. Neuhold, John F. Marchaterre, Alan E. Waltar
Nuclear Technology | Volume 89 | Number 1 | January 1990 | Pages 83-91
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34360
Development of a Three-Dimensional Transient Code for Reactivity-Initiated Events of Boiling Water Reactors—Two Rod Drop Accident Analyses
Sadayuki Izutsu, Yoshiro Kudo, Junichi Onuma, Tomohiko Iwasaki, Sakae Muto, Akio Toba
Nuclear Technology | Volume 89 | Number 1 | January 1990 | Pages 92-102
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34361
An Experimental Investigation on Turbulent Flow Through Symmetric Wall Subchannels of Two Rod Bundles
Shao-Rong Wu, Klaus Rehme
Nuclear Technology | Volume 89 | Number 1 | January 1990 | Pages 103-115
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34362
Destructive Gamma-Ray Analysis of Fuel Rods from the Taiwan Research Reactor
Lung-Kwang Pan
Nuclear Technology | Volume 89 | Number 1 | January 1990 | Pages 116-125
Technical Paper | Technique | doi.org/10.13182/NT90-A34363
An Expert System to Estimate Time, Rate, and Magnitude of Release of Important Radioactive Isotopes Given a Loss of Containment Integrity
Kil-Yoo Kim, David Okrent
Nuclear Technology | Volume 89 | Number 1 | January 1990 | Pages 126-129
Technical Note | Nuclear Safety | doi.org/10.13182/NT90-A34364
Advances in Technology for Storing Light Water Reactor Spent Fuel
E. Robert Gilbert, Wendell J. Bailey, A. Burtron Johnson, Jr., Mikal A. McKinnon
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 141-161
Technical Paper | Fuel Cycle | doi.org/10.13182/NT90-A34342
Construction of the Monju Prototype Fast Breeder Reactor
Tadao Takahashi, Osamu Yamaguchi, Tetsuo Kobori
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 162-176
Technical Paper | Fission Reactor | doi.org/10.13182/NT90-A34343
A Comparison of RELAP5/MOD2 Results to the Data of a Small-Break Loss-of-Coolant Accident Experiment of an IAEA Standard Problem Exercise
Sandra M. Sloan, Yassin A. Hassan
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 177-182
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34344
Development of the SESAME Metallic Fuel Performance Code
Tsuguyuki Kobayashi, Motoyasu Kinoshita, Sadao Hattori, Toru Ogawa, Yasushi Tsuboi, Masayoshi Ishida, Shinta Ogawa, Hiroaki Saito
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 183-193
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34345
Present Status of Fast Breeder Reactor Fuel Cycle Development at PNC
Masao Yamamoto, Ken-Ichi Matsumoto
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 194-202
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34346
A Remote Canister-Positioning and Glass Level Detection System
Ronald W. Goles, Peter J. Hof, Richard D. Dierks, Langdon K. Holton
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 203-216
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT90-A34347
Identification of Two-Phase Flow Patterns in a Nuclear Reactor by High-Frequency Contribution Fraction
Y. W. Wang, B. S. Pei, C. H. King, S. C. Lee
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 217-226
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34348
A Proposed Calculational Model for Two-Phase Countercurrent Flow Limitation in Channels with Abrupt Area Change
Tanvir Salim, Woon-Shing Yeung, R. Thomas Fernandez
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 227-232
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34349
An Intelligent Stochastic Optimization Routine for Nuclear Fuel Cycle Design
Geoffrey Thomas Parks
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 233-246
Technical Paper | Technique | doi.org/10.13182/NT90-A34350
Image Reconstruction for a Radiation Field Mapping Device
Robert Gould, Edward S. Kenney
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 247-251
Technical Paper | Technique | doi.org/10.13182/NT90-A34351
GPU Nuclear Corporation Licensed Operator Requalification Program Using the Penn State Breazeale Nuclear Reactor
Samuel H. Levine, Terry L. Flinchbaugh, John L. Penkala, Daniel E. Hughes, Kenneth E. Rudy, Craig C. Faust, Ronald H. Maag
Nuclear Technology | Volume 89 | Number 2 | February 1990 | Pages 252-267
Technical Paper | Education | doi.org/10.13182/NT90-A34352
The Computer-Aided Design System Used for the Design of the Chooz B Nuclear Power Plant Control System
P. Bacher, G. Beltranda
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 275-280
Technical Paper | Fission Reactor | doi.org/10.13182/NT90-A34367
An Integrated Operator Advisor System For Plant Monitoring, Procedure Management, and Diagnosis
Rajiv Bhatnagar, Don W. Miller, Brian K. Hajek, and, John E. Stasenko
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 281-317
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34368
Rapid Simulation of Concentration Profiles in Pulsed Column Contactors Using the Purex Process
John F. Geldard, Adolph L. Beyerlein
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 318-327
Technical Paper | Chemical Processing | doi.org/10.13182/NT90-A34369
An Incinerator Ash Dissolution Model for the System: Plutonium Oxide, Nitric and Hydrofluoric Acids
Eric V. Brown, Leonard W. Gray, D. William Tedder
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 328-340
Technical Paper | Chemical Processing | doi.org/10.13182/NT90-A34370
The Back End of the Nuclear Fuel Cycle: Technical and Economic Analysis—Part I: Once-Through Cycle
Jordi Roglans-Ribas, Bernard I. Spinrad
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 341-349
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34371
The Back End of the Nuclear Fuel Cycle: Technical and Economic Analysis—Part II: Comparison of Cycles
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 350-357
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34372
Dissolution Model for a Glass Having an Adherent Insoluble Surface Layer
Keith B. Harvey, Carol A. B. Larocque
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 358-364
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT90-A34373
An Alkaline Prefilming Process for the Primary Piping in a New Japanese Boiling Water Reactor
Takashi Honda, Katsumi Ohsumi, Motohiro Aizawa, Kiichiro Takagi, Osamu Amano, Kazuhiko Yamashita
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 365-371
Technical Paper | Material | doi.org/10.13182/NT90-2
Energy Consumption for Product Assay in a Chemical Enrichment Process
Kunihiko Takeda, Yoshikazu Nishigaki, Hatsuki Onitsuka
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 372-380
Technical Paper | Radioisotopes and Isotope Separation | doi.org/10.13182/NT90-A34375
Isotopic Backmixing in a Large-Scale Enrichment Column in a Chemical Enrichment Method
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 381-387
Technical Paper | Radioisotopes and Isotope Separation | doi.org/10.13182/NT90-A34376
Transient Condensation in the Presence of Noncondensables at a Vertical Wall
Suresh V. Garimella, Richard N. Christensen
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 388-398
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34377
Controlled Potential Coulometric Determination of Plutonium in Mixed (U, Pu) Carbide Fuels
Har Swroop Sharma, Nandakumar B. Khedekar, Surendranath G. Marathe, Hem Chand Jain
Nuclear Technology | Volume 89 | Number 3 | March 1990 | Pages 399-405
Technical Paper | Technique | doi.org/10.13182/NT90-A34378
