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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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A Movable Boundary Model for Once-Through Steam Generator Analysis
Constantine P. Tzanos
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 5-17
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34113
Turbine Missiles Assessment
Truong V. Vo
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 21-35
Technical Paper | Nuclear Safety | doi.org/10.13182/NT88-A34114
The Intercomparison of Aerosol Codes
Ian H. Dunbar, Jean Fermandjian, Jean Gauvain
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 36-51
Technical Paper | Nuclear Safety | doi.org/10.13182/NT88-A34115
A Thermodynamic Model of Nitric Acid Extraction by Tri-n-Butyl Phosphate
David J. Chaiko, George F. Vandegrift
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 52-59
Technical Paper | Chemical Processing | doi.org/10.13182/NT88-A34116
Gas Migration from Low-Level Radioactive Waste Repositories in Hard Rocks
Carol Braester, Roger Thunvik
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 60-70
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT88-A34117
Model Calculations of the Thermomechanical Effects in the Near Field of a High-Level Radioactive Waste Repository
Alexandra Pudewills, Ekkehard Korthaus, Rainer H. Köster
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 71-80
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT88-A34118
Pilot Testing of Radioluminescent Lights for Remote Airfields
George A. Jensen, R. F. Hazelton, R. G. Moles
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 81-93
Technical Paper | Radioisotope and Isotope Separation | doi.org/10.13182/NT88-A34119
A Comparison of Two Efficient Nonlinear Heat Conduction Methodologies Using a Two-Dimensional Time-Dependent Benchmark Problem
Gary L. Wilson, Roger A. Rydin, Seppo Orivuori
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 94-105
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34120
Radiation Dose Impacts Resulting from Variations in the Transportation-Related Activities in a System for Management of Spent Nuclear Fuel
Kenneth J. Schneider, Peter J. Pelto, Jay C. Lavender, Philip M. Daling, Barbara A. Fecht
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 106-113
Technical Note | Radioactive Waste Management | doi.org/10.13182/NT88-A34121
Real-Time Data Logging and Color Graphics Display Systems for a Boiling Water Reactor Simulator
Alireza Behbahani, Jeffery Reagan
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 121-131
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34101
A Method of State Transition Analysis Under System Interactions: An Analysis of a Shutdown Heat Removal System
Kotaro Nakada, Kazumi Miyagi, Norihiko Handa, Sadao Hattori
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 132-146
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34102
Conceptual Design and Thermal-Hydraulic Characteristics of Natural Circulation Boiling Water Reactors
Yoshiyuki Kataoka, Hiroaki Suzuki, Michio Murase, Isao Sumida, Tetsuo Horiuchi, Minoru Miki
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 147-156
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34103
Radiolysis of Cesium Iodide Solutions in Conditions Prevailing in a Pressurized Water Reactor Severe Accident
Michel Lucas
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 157-161
Technical Paper | Nuclear Safety | doi.org/10.13182/NT82-157
An Expert System Approach for Safety Diagnosis
R. C. Erdmann, Bill K-H. Sun
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 162-172
Technical Paper | Nuclear Safety | doi.org/10.13182/NT88-A34105
OREST—The HAMMER-ORIGEN Burnup Program System: Method and Results
Ulrich Hesse
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 173-186
Technical Paper | Fuel Cycle | doi.org/10.13182/NT88-A34106
Variational Determination of Transient Radial-Azimuthal Temperature Distributions in Fuel Rods for Loss-of-Coolant-Accident Analysis
Nicholas T. Saltos, Tunc Aldemir, Richard N. Christensen
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 187-210
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT88-A34107
Identification of Two-Phase Flow Regimes by an Optimum Modeling Method
C. H. King, M. S. Ouyang, B. S. Pei, Y. W. Wang
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 211-226
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34108
Investigation of the Bubbly Air/Water Flow Using the Chord-Segment Inversion Algorithm
R. K. S. Rathore, P. Munshi, R. K. Jarwal, I. D. Dhariyal
Nuclear Technology | Volume 82 | Number 2 | August 1988 | Pages 227-234
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34109
Removal of Aluminum Turbidity from Heavy Water Reactors by Precipitation Ion Exchange Using Magnesium Hydroxide
Kasibhatla Sri Venkateswarlu, Ramendra Shanker, Sankaralingam Velmurugan, Gopala Venkateswaran, Mysore Ranganatha Rao
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 243-250
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34125
Development of a Four-Equation Reactor Coolant System Model for Pressurized Water Reactor Simulation
Mankit Ray Yeung, Ping Lam Chan
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 251-257
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34126
Core Physics of a Small Boiling Water Reactor for District Heating
Alex Galperin, Constantine G. Foskolos, Peter Grimm
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 258-266
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34127
A Point Reactivity Model for In-Core Fuel Cycles
Geoffrey Thomas Parks, Jeffery David Lewins
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 267-274
Technical Paper | Fuel Cycle | doi.org/10.13182/NT88-A34128
A Gauge for Nondestructive Assay of Irradiated Fuel Rods
George Tessler, Ben R. Beaudoin, William J. Beggs, Louis B. Freeman, Albert C. Kahler, William C. Schick, Jr.
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 275-289
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT88-A34129
Fracture Toughness of Irradiated Stainless Steel Alloys
W. J. Mills
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 290-303
Technical Paper | Material | doi.org/10.13182/NT88-A34130
Description and Analysis of an Accelerator-Based Production Method of the Brachytherapy Source 145Sm
Thomas E. Blue
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 304-310
Technical Paper | Radioisotopes and Isotope Separation | doi.org/10.13182/NT88-A34131
Dose Estimates from the Chernobyl Accident
Rolf Lange, Marvin H. Dickerson, Paul H. Gudiksen
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 311-323
Technical Paper | Radiation Biology and Environment | doi.org/10.13182/NT88-A34132
A Computerized System for Continuous Monitoring of the Core Cooling Margin
Luiz Rogério Araujo de Araujo, Aquilino Senra Martinez, Roberto Schirru, Renato Kahn
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 324-329
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34133
Onset of Nucleate Boiling in Research Reactors with Thin Rectangular Channels Under Low-Velocity Upward-Flow Conditions
Mohamed Belhadj, Tunc Aldemir, Richard N. Christensen
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 330-340
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34134
Reproducibility in a Multiloop Thermal-Hydraulic System
Kazys K. Almenas, Yih-Yun Hsu, Marino Dimarzo, Zen-You Wang, Gary A. Pertmer, Richard Lee
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 341-354
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT88-A34135
Real-Time Neutron Radiography System Performance—Measurements and Methods
Mark F. Sulcoski, Kenneth W. Tobin, Jack S. Brenizer, Jr.
Nuclear Technology | Volume 82 | Number 3 | September 1988 | Pages 355-362
Technical Paper | Analyse | doi.org/10.13182/NT88-A34136
