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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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Automatic Determination of Pressurized Water Reactor Core Loading Patterns That Maximize Beginning-of-Cycle Reactivity Within Power-Peaking and Burnup Constraints
Gregory H. Hobson, Paul J. Turinsky
Nuclear Technology | Volume 74 | Number 1 | July 1986 | Pages 5-13
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33814
Shielding Designs for Pressurized Water Reactors in France
Gilles Champion, Josette Forestier, Thérèse Vergnaud
Nuclear Technology | Volume 74 | Number 1 | July 1986 | Pages 14-26
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33815
A Study on Fuel Rod Vibration Induced by Baffle Jet Flow
Kazuichiro Seki, Shigeru Kuwabara, Katsumi Tanimura, Shinsuke Matsumoto, Masao Toba
Nuclear Technology | Volume 74 | Number 1 | July 1986 | Pages 27-37
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33816
Stability Tests at Browns Ferry Unit 1 Under Single-Loop Operating Conditions
Jose March-Leuba, Richard T. Wood, Pedro J. Otaduy, Clayton O. McNew
Nuclear Technology | Volume 74 | Number 1 | July 1986 | Pages 38-52
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33817
Experience in the Use of Probabilistic Safety Analysis for the Development of Safety Concepts for Commercial High-Temperature Reactors
Wolfgang Kröger, Johannes P. Wolters
Nuclear Technology | Volume 74 | Number 1 | July 1986 | Pages 53-64
Technical Paper | Neuclear Safety | doi.org/10.13182/NT86-A33818
Computer Simulation of a Large-Scale Reprocessing Plant for Safeguards
G. Spannagel, M. J. Canty, E. A. Kern
Nuclear Technology | Volume 74 | Number 1 | July 1986 | Pages 65-75
Technical Paper | Fuel Cycle | doi.org/10.13182/NT86-A33819
Role of Surface Vaporization in Low-Volatility Fission Product Release Experiments
A. B. Reynolds, J. L. Kelly, S. T. Kim
Nuclear Technology | Volume 74 | Number 1 | July 1986 | Pages 76-83
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A33820
The Effect of Fast-Neutron Irradiation on the Fatigue-Crack Growth Behavior of Several Austenitic Stainless Steels and Weldments
Lee A. James
Nuclear Technology | Volume 74 | Number 1 | July 1986 | Pages 84-92
Technical Paper | Material | doi.org/10.13182/NT86-A33821
Simulation of Heat and Mass Transfer in Molten Core/Concrete Interactions
I. K. Paik, S. I. Abdel-Khalik
Nuclear Technology | Volume 74 | Number 1 | July 1986 | Pages 93-103
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT86-A33822
Development of a Combined Algorithm of On-Line Instrument Failure Detection with an Improved Generalized Likelihood Ratio Method and Suboptimal Control on a PWR Pressurizer
Hack Yeong Chung, Soon Heung Chang
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 113-131
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33797
Applicability of a Multivariable Autoregressive Method to Boiling Water Reactor Core Stability Estimation
Satoshi Suzuki, Kohyu Fukunishi, Shoichi Kishi, Yuichiro Yoshimoto, Kunikazu Kishimoto
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 132-138
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33798
An Application of Nonlinear Filtering to Instrument Failure Detection in a Pressurized Water Reactor
Steven J. Eckert, Kenneth A. Loparo, Zvi S. Roth
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 139-151
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33799
Evaluation of the Tritium Content in Light Water Reactor Control and Absorber Rods to Obtain Data for the Fuel Cycle Backend
Alois Bleier, Karl Heinz Neeb, Eike Gelfort, Joachim Mischke
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 152-163
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33800
Measurement of Dose Rates and Monte Carlo Analysis of Neutrons in a Spent-Fuel Shipping Vessel
Kohtaro Ueki, Yoshihito Namito, Takayoshi Fuse
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 164-175
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A33801
Analysis of FLECHT and FLECHT-SEASET Reflood Tests with RELAP5/MOD2
Yassin A. Hassan*
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 176-188
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A33802
The Influence of Particle Phase Size on the Disassembly Accident Transient in Fast Reactors
Subhash Chandra
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 189-194
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A33803
Dynamic Logical Analytical Methodology Versus Fault Tree: The Case Study of the Auxiliary Feedwater System of a Nuclear Power Plant
P. C. Cacciabue, A. Amendola, G. Cojazzi
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 195-208
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A33804
In Situ Investigations on the Impact of Heat Production and Gamma Radiation with Regard to High-Level Radioactive Waste Disposal in Rock Salt Formations
T. Rothfuchs
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 209-214
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33805
Oxidation of UO2 by High-Pressure Steam
D. R. Olander
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 215-217
Technical Paper | Material | doi.org/10.13182/NT86-A33806
Moments Analysis Method for the Determination of Dimensions from Radiographs
Yossi Bushlin, Dov Ingman, Amos Notea
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 218-228
Technical Paper | Technique | doi.org/10.13182/NT86-A33807
On Farmer’s Line, Probability Density Functions, and Overall Risk
Hector A. Munera, George Yadigaroglu
Nuclear Technology | Volume 74 | Number 2 | August 1986 | Pages 229-232
Technical Note | Nuclear Safety | doi.org/10.13182/NT86-A33808
An Approach of Statistical Thermodynamics to Effects of Coherent Blockages of Reactor Core Coolant Channels
Dov Ingman, Leib Reznik
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 243-259
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33827
A Nonequilibrium Three-Region Model for Transient Analysis of Pressurized Water Reactor Pressurizer
Seung Min Baek, Hee Cheon No, In Yong Park
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 260-266
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33828
The Availability of Neutron Channels and Power Range Monitoring Systems with In Situ Detection of Channel Degradation
Tunc Aldemir, Don W. Miller
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 267-271
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33829
Reliability and Risk Allocation in Nuclear Power Plants: A Decision-Theoretic Approach
I. A. Papazoglou, N. Z. Cho, R. A. Bari
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 272-286
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33830
Accelerated High-Temperature Tests with Spent PWR and BWR Fuel Rods Under Dry Storage Conditions
Gerd Porsch, Joachim Fleisch, Bernd Heits
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 287-298
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A33831
Leaching of SYNROC-C: Relation to Microstructures
Takashi Murakami, Tsunetaka Banba, Haruto Nakamura
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 299-306
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33832
Neptunium Migration in Salt Brine Aquifers
Giovanni Bidoglio, Alfonso De Plano
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 307-316
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33833
Diffusion of Tritiated Water and Chloride in Basalt-Bentonite Mixtures
John F. Relyea, David P. Trott, C. V. McIntyre, Craig G. Rieger
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 317-323
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33834
A Chemical Decontamination Process for Decontaminating and Decommissioning Nuclear Reactors
Alexander P. Murray
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 324-332
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33835
Safety Margins in Zircaloy Oxidation and Embrittlement Criteria for Emergency Core Cooling System Acceptance
R. E. Williford
Nuclear Technology | Volume 74 | Number 3 | September 1986 | Pages 333-345
Technical Paper | Material | doi.org/10.13182/NT86-A33836
