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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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Investigation of Two-Phase Phenomena Occurring Within Moisture Separator Reheater High-Level Reactor Trips at the Maanshan Nuclear Power Plant
Yuh-Ming Ferng, Lih-Yih Liao
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 1-13
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35194
Westinghouse-Gothic Comparisons with Passive Containment Cooling Tests Using a One-to-Ten-Scale Test Facility
M. D. Kennedy, J. Woodcock, R. F. Wright, J. A. Gresham
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 14-20
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35195
Development of a MELCOR Self-Initialization Algorithm for Boiling Water Reactors
Chun-Sheng Chien, Shih-Jen Wang, Shih-Kuei Cheng
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 21-28
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35196
A Model for Container Performance in an Unsaturated Repository
Daniel B. Bullen
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 29-45
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35197
Ambient Temperature Contamination of Process Piping and the Effects of Pretreatment
S. A. Adeleye, D. A. White, J. B. Taylor
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 46-53
Technical Paper | Material | doi.org/10.13182/NT96-A35198
Development of Thermohydraulics Computer Programs for Thermal Striping Phenomena
Toshiharu Muramatsu, Hisashi Ninokata
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 54-72
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35199
Modeling the Accumulators of the Advanced Neutron Source Reactor
R. L. Moore, C. D. Fletcher, C. S. Miller
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 73-85
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35200
Characterization of Anomalies by Applying Methods of Fractal Analysis
M. Sakuma, R. Kozma, M. Kitamura
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 86-99
Technical Paper | Reactor Operation | doi.org/10.13182/NT96-A35201
Myth or Nightmare: Safety Consequences of the Release of Radiation-Induced Stored Energy in Rock Salt
J. Prij
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 100-109
Technical Note | Radioactive Waste Management | doi.org/10.13182/NT96-A35202
Critical Mass Variation of 239Pu with Water Dilution
Sol Pearlstein
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 110-111
Technical Note | Nuclear Criticality Safety | doi.org/10.13182/NT96-A35203
The Selection of Fixed-Order Quadratures in Point-Kernel Shielding Calculations
O. J. Wallace
Nuclear Technology | Volume 113 | Number 1 | January 1996 | Pages 112-122
Technical Note | Radiation Protection | doi.org/10.13182/NT96-A35204
Passive Pressure Tube Light Water Reactors
Pavel Hejzlar, Neil E. Todreas, Michael J. Driscoll
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 123-133
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35182
Large Passive Pressure Tube Light Water Reactor with Voided Calandria
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 134-144
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35183
Estimation of Dynamic Reactivity Using an H∞ Optimal Filter with a Nonlinear Term
Katsuo Suzuki, Koiti Watanabe
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 145-154
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35184
Modeling of Diffusive Gravitational Aerosol Deposition in CONTAIN
Almir Fernandes, Sudarshan K. Loyalka
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 155-166
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35185
Validation Studies of a Computational Model for Molten Material Freezing
Tetsuo Sawada, Hisashi Ninokata, Akinao Shimizu
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 167-176
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35186
Degradation Analysis Estimates of the Time-to-Failure Distribution of Irradiated Fuel Elements
Abdellatif M. Yacout, Stefano Salvatores, Yuri Orechwa
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 177-189
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT96-A35187
A Set of Integrated Environmental Transport and Diffusion Models for Calculating Hazardous Releases
Darrell W. Pepper, James A. Marino
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 190-203
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35188
On the French Project Developed in the 1980s for the Production of 99Mo from the Fission of 235U
J. Bourges, C. Madic, G. Koehly, T. H. Nguyen, D. Baltes, C. Landesman, A. Simon
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 204-220
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT96-A35189
Gaseous Radioiodine Deposition Losses in Nuclear Reactor Sample Lines
Byung-Soo Lee, William A. Jester
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 221-231
Technical Paper | Reactor Operation | doi.org/10.13182/NT96-A35190
A Personal Computer—Based On-Line Balance-of-Plant Performance Monitoring and Analysis System for Nuclear Power Plants
Gung-Huei Chou, Jin-Yeh Hsu, Houng-June Chao
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 232-241
Technical Paper | Reactor Operation | doi.org/10.13182/NT96-A35191
Analysis of Core Uncovery Time in Kuosheng Station Blackout Transient with MELCOR
Shih-Jen Wang, Chun-Sheng Chien
Nuclear Technology | Volume 113 | Number 2 | February 1996 | Pages 242-248
Technical Note | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35192
Wind Effects on the Performance of the Reactor Vessel Auxiliary Cooling System
C. P. Tzanos, A. Hunsbedt
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 249-267
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35206
SASSYS/SAS4A-FPIN2 Liquid-Metal Reactor Transient Analysis Code System for Mechanical Analysis of Metallic Fuel Elements
Tanju Sofu, John M. Kramer, James E. Cahalan
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 268-279
Technical Paper | Fission Reactor | doi.org/10.13182/NT96-A35207
Use of the Chinshan Plant Analyzer for Analysis of a Main-Steam-lsolation-Valve-Closure Anticipated Transient Without Scram
Shih-Jen Wang, Shih-Hsiin Chang, Ling-Yao Chou
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 280-290
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35208
Experience with COSYMA in an International Intercomparison of Probabilistic Accident Consequence Assessment Codes
I. Hasemann, J. A. Jones, J. Van Der Steen, E. Van Wonderen
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 291-303
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT96-A35209
Thermal Decomposition of Nitrated Tributyl Phosphate
Y. Hou, E. K. Barefield, D. W. Tedder, S. I. Abdel-Khalik
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 304-315
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT96-A35210
Sensitivity of the Radionuclide Release from a Repository to the Variability of Materials and Other Properties
Leonardo Romero, Luis Moreno, Ivars Neretnieks
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 316-326
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT96-A35211
Two-Phase Flow Instability for Low-Flow Boiling in Vertical Uniformly Heated Thin Rectangular Channels
Chang H. Oh, John C. Chapman
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 327-337
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35212
A Passive System for Long-Term Heat Removal in Advanced Light Water Reactors: Prototype Test Results and Analysis
Luca Galbiati, Luigi Mazzocchi, Paolo Vanini
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 338-345
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT96-A35213
Rapid Measurement of the Gaseous 41Ar Released from a Nuclear Reactor Using a Portable Spectrometer
Chien Chung, Chin-Hsuen Tsai
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 346-353
Technical Paper | Radiation Protection | doi.org/10.13182/NT96-A35214
Optimization of Standby Safety System Maintenance Schedules in Nuclear Power Plants
Mohammad Harunuzzaman, Tunc Aldemir
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 354-367
Technical Paper | Reactor Operation | doi.org/10.13182/NT96-A35215
Multiple-Failure Signal Validation in Nuclear Power Plants Using Artificial Neural Networks
Paolo F. Fantoni, Alessandro Mazzola
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 368-374
Technical Paper | Reactor Operation | doi.org/10.13182/NT96-A35216
Modified Conversion Ratio Measurement in Light Water-Moderated UO2 Lattices
Ken Nakajima, Masanori Akai
Nuclear Technology | Volume 113 | Number 3 | March 1996 | Pages 375-379
Technical Note | Fission Reactor | doi.org/10.13182/NT96-A35217
