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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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Criticality Safety Evaluation for High-Density Spent-Fuel Storage Racks
Tien-Ko Wang, Szu-Li Chang, Shi-Ping Teng
Nuclear Technology | Volume 83 | Number 1 | October 1988 | Pages 5-15
Technical Paper | Nuclear Safety | doi.org/10.13182/NT88-A34170
The Growth of Hygroscopic Particles During Severe Core Melt Accidents
Jorma Jokiniemi
Nuclear Technology | Volume 83 | Number 1 | October 1988 | Pages 16-23
Technical Paper | Nuclear Safety | doi.org/10.13182/NT88-A34171
The Composition of NOx Generated in the Dissolution of Uranium Dioxide
Tsutomu Sakurai, Akira Takahashi, Niro Ishikawa, Yoshihide Komaki
Nuclear Technology | Volume 83 | Number 1 | October 1988 | Pages 24-30
Technical Paper | Fuel Cycle | doi.org/10.13182/NT88-A34172
Out-of-Core Fuel Cycle Optimization for Nonequilibrium Cycles
Scott A. Comes, Paul J. Turinsky
Nuclear Technology | Volume 83 | Number 1 | October 1988 | Pages 31-48
Technical Paper | Fuel Cycle | doi.org/10.13182/NT88-A34173
Development and Active Demonstration of Acid Digestion of Plutonium- Bearing Waste
Herbert Wieczorek, Bernhard Oser
Nuclear Technology | Volume 83 | Number 1 | October 1988 | Pages 49-55
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT88-A34174
Identification of Two-Phase Flow Patterns by a Single Void Fraction Sensor
Y. W. Wang, C. H. King, B. S. Pei
Nuclear Technology | Volume 83 | Number 1 | October 1988 | Pages 56-64
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34175
IVA2 Verification: High-Pressure Gas Injection in a Liquid Pool
Nikolay Ivanov Kolev
Nuclear Technology | Volume 83 | Number 1 | October 1988 | Pages 65-80
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34176
Development of Computer Program DYNAM/US for Predicting Thermally Induced Flow Oscillations in Two-Phase Flow Systems
S. M. Sami, M. Kraitem
Nuclear Technology | Volume 83 | Number 1 | October 1988 | Pages 81-92
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34177
Determination of Transient Radial-Azimuthal Temperature Distributions in Fuel Bundles Under Loss-of-Coolant-Accident Conditions
Nicholas T. Saltos,* Richard N. Christensen, Tunc Aldemir
Nuclear Technology | Volume 83 | Number 1 | October 1988 | Pages 93-109
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34178
Filtered Vented Containment Systems for Light Water Reactors
Harry A. Morewitz
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 117-133
Technical Paper | Critical Review | doi.org/10.13182/NT88-A34155
Assessment of Long-Term Reliability of Pressurized Water Reactor Plants Based on Power Generation Statistics (Up to 1987)
Masahiro Matsumura
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 134-161
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34156
Study on Criticality of a Light Water Moderated and Reflected Coupled Core with Highly Enriched Uranium Fuel
Tsuyoshi Misawa, Seiji Shiroya, Keiji Kanda
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 162-170
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34157
Experimental and Theoretical Evidence for a Short Effective Fuel Time Constant in a Boiling Water Reactor
Tim H. J. J. van der Hagen
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 171-181
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34158
Secondary Purex Solvent Cleanup: Laboratory Development
James C. Mailen
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 182-189
Technical Paper | Fuel Cycle | doi.org/10.13182/NT88-A34159
Canyon Solvent Cleaning with Activated Alumina
Donald J. Reif
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 190-196
Technical Paper | Chemical Processing | doi.org/10.13182/NT88-A34160
Analysis of Mechanical Bowing Phenomena of Fuel Assemblies in Passively Safe Advanced Liquid-Metal Reactors
Per G. Reinhall, Kwanhum Park, Robert W. Albrecht
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 197-204
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT88-A34161
Improved Treatment/Disposal of Reactive Metals
John B. Rajan, Romesh Kumar, Donald R. Vissers
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 205-211
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT88-A34162
The Economic Impact of the Utilization of Nuclear Power Plant Condensation Heat
Ahmet Bayülken
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 212-215
Technical Paper | Economic | doi.org/10.13182/NT88-A34163
Characterization of Reaction Gases and Aerosols from Underwater Plasma Arc Cutting Demonstration Tests at Three Mile Island Unit 2
V. F. Baston, K. J. Hofstetter, Richard F. Karuhn
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 216-227
Technical Paper | Material | doi.org/10.13182/NT88-A34164
Higher Order Tomographic Filters for Nondestructive Testing Purposes
P. Arora, P. Munshi, R. K. S. Rathore
Nuclear Technology | Volume 83 | Number 2 | November 1988 | Pages 228-230
Technical Note | Technique | doi.org/10.13182/NT88-A34165
Overview of 1986–1987 RETRAN Activity
Lance J. Agee
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 241-251
Overview | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34139
RETRAN Application for Issue Resolution
Peter J. Jensen, V. K. Chexal, Jason Chao, William H. Layman
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 252-273
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34140
Features of the RETRAN-03 Computer Code
M. P. Paulsen, B. E. Griebenow, L. R. Feinauer, J. H. McFadden, Peter J. Jensen
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 274-288
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34141
An Analysis of the Chernobyl Accident Using RETRAN-02/MOD3
Jason Chao, V. K. Chexal, William H. Layman, Gary Vine, Peter J. Jensen, Adi R. Dastur
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 289-301
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34142
Results of Carolina Power and Light Company’s Analysis of Brunswick Unit 1 Start-Up Tests Using RETRAN
Steven J. Ganthner, A. Frank Wenger
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 302-309
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34143
Qualification of RETRAN for Simulator Applications
James F. Harrison
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 310-324
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34144
Qualification of a RETRAN-02 Model for Cofrentes
J. J. Martínez Caballero, Pablo García Sedano
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 325-333
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34145
RETRAN Applications at Florida Power & Light to Support Operations and Training
Jorge Arpa, Jose Ramos, Juan R. Villar
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 334-343
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34146
Qualification of the Oconee RETRAN Model by Comparison with Plant Transient Data
Steven P. Nesbit, Richard J. Gerling, Gregg B. Swindlehurst
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 344-352
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34147
Oyster Creek RETRAN Licensing Model Development
Mansur A. Alammar, Ronald V. Furia, Jimmy H. Chin, Chandrakant B. Mehta
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 353-366
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34148
RETRAN Modeling of the Pressurized Water Reactor Control Rod Ejection Transient
Joseph O. Erb, James G. Miller
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 367-373
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34149
Boiling Water Reactor Core Stability Analysis with RETRAN
Shie-Jeng Peng
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 374-382
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34150
Boiling Water Reactor Stability Analysis with RETRAN
John Sorensen
Nuclear Technology | Volume 83 | Number 3 | December 1988 | Pages 383-395
Technical Paper | Fifth International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34151
