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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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BWR Regional Instability Analysis by TRAC/BF1-ENTRÉE - I: Application to Density-Wave Oscillation
Akitoshi Hotta, Makoto Honma, Hisashi Ninokata, Yusuke Matsui
Nuclear Technology | Volume 135 | Number 1 | July 2001 | Pages 1-16
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3202
BWR Regional Instability Analysis by TRAC/BF1-ENTRÉE - II: Application to Ringhals Unit-1 Stability Test
Akitoshi Hotta, Minyan Zhang, Hisashi Ninokata
Nuclear Technology | Volume 135 | Number 1 | July 2001 | Pages 17-38
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3203
Parallel Computing Adaptive Simulated Annealing Scheme for Fuel Assembly Loading Pattern Optimization in PWRs
Hyun Chul Lee, Hyung Jin Shim, Chang Hyo Kim
Nuclear Technology | Volume 135 | Number 1 | July 2001 | Pages 39-50
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3204
Thermal-Hydraulic Analysis of the 3-MW TRIGA MARK-II Research Reactor Under Steady-State and Transient Conditions
M. Q. Huda, S. I. Bhuiyan, T. K. Chakrobortty, M. M. Sarker, M. A. W. Mondal
Nuclear Technology | Volume 135 | Number 1 | July 2001 | Pages 51-66
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3205
An Innovative Fuzzy-Logic-Based Methodology for Trend Identification
Xin Wang, Lefteri H. Tsoukalas, Thomas Y. C. Wei, Jaques Reifman
Nuclear Technology | Volume 135 | Number 1 | July 2001 | Pages 67-84
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT01-A3206
Seismic Design and Analysis of the Support System of the HTR-10 Primary Loop Boundary Components
Zheng-Ming Zhang, Min-Zhi Wang, Shu-Yan He
Nuclear Technology | Volume 135 | Number 2 | August 2001 | Pages 85-91
Technical Paper | Fission Reactors | doi.org/10.13182/NT01-A3207
Characterization of the Mobilities of Selected Actinides and Fission/Activation Products in Laboratory Columns Containing Subsurface Material from the Snake River Plain
Robert A. Fjeld, Timothy A. DeVol, Russell W. Goff, Matthew D. Blevins, David D. Brown, Steven M. Ince, Alan W. Elzerman, Meredith E. Newman
Nuclear Technology | Volume 135 | Number 2 | August 2001 | Pages 92-108
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3208
Using an IIST 1% Cold-Leg SBLOCA Experiment with Passive Safety Injection to Assess the RELAP5/MOD3.2 Code
Chien-Hsiung Lee, I-Ming Huang, Chin-Jang Chang
Nuclear Technology | Volume 135 | Number 2 | August 2001 | Pages 109-122
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3209
The EOP Visualization Module Integrated into the Plasma On-Line Nuclear Power Plant Safety Monitoring and Assessment System
Arne Hornaes, John Einar Hulsund, János Végh, Csaba Major, Csaba Horváth, Sándor Lipcsei, György Kapocs
Nuclear Technology | Volume 135 | Number 2 | August 2001 | Pages 123-130
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT01-A3210
A Tomographic Method for Verification of the Integrity of Spent Nuclear Fuel Assemblies - I: Simulation Studies
Staffan Jacobsson, Camilla Andersson, Ane Håkansson, Anders Bäcklin
Nuclear Technology | Volume 135 | Number 2 | August 2001 | Pages 131-145
Technical Paper | Enrichment | doi.org/10.13182/NT01-A3211
A Tomographic Method for Verification of the Integrity of Spent Nuclear Fuel Assemblies - II: Experimental Investigation
Staffan Jacobsson, Ane Håkansson, Peter Jansson, Anders Bäcklin
Nuclear Technology | Volume 135 | Number 2 | August 2001 | Pages 146-153
Technical Paper | Enrichment | doi.org/10.13182/NT01-A3212
Effect of Water Radiolysis Caused by Dispersed Radionuclides on Oxidative Dissolution of Spent Fuel in a Final Repository
Jinsong Liu, Ivars Neretnieks
Nuclear Technology | Volume 135 | Number 2 | August 2001 | Pages 154-161
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-A3213
Blanket Design Studies of a Lead-Bismuth Eutectic-Cooled Accelerator Transmutation of Waste System
Won Sik Yang, Hussein S. Khalil
Nuclear Technology | Volume 135 | Number 2 | August 2001 | Pages 162-182
Technical Paper | Accelerators | doi.org/10.13182/NT135-162
Source Term Estimation for Small-Sized HTRs: Status and Further Needs, Extracted from German Safety Analyses
Rainer Moormann, Werner Schenk, Karl Verfondern
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 183-193
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3215
Criticality Behavior of Dilute Plutonium Solutions
Christopher C. Pain, Cassiano R. E. de Oliveira, Antony J. H. Goddard, Adrian P. Umpleby
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 194-215
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3216
Nondestructive Assay of Nuclear Low-Enriched Uranium Spent Fuels for Burnup Credit Application
Alain Lebrun, Gilles Bignan
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 216-229
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3217
An Estimation Method for Off-Gas Sources in a Boiling Water Reactor with Nondefective Fuel
Masato Takahashi
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 230-240
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3218
FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package III
Atul A. Karve, Paul J. Turinsky
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 241-251
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3219
Refinement of Transient Criteria and Safety Analysis for a High-Temperature Reactor Cooled by Supercritical Water
Kazuaki Kitoh, Seiichi Koshizuka, Yoshiaki Oka
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 252-264
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3220
KAMINI Reactor South Beam Port Shield-Structure Optimization
K. V. Subbaiah, C. Sunil Sunny
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 265-272
Technical Paper | Radiation Protection | doi.org/10.13182/NT01-A3221
A Coupled Model for Oxidative Dissolution of Spent Fuel and Transport of Radionuclides from an Initially Defective Canister
Longcheng Liu, Ivars Neretnieks
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 273-285
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-2
Boron Carbide Deposition on Urania and Urania-Gadolinia Fuels
H. Disbudak, I. Uslu, A. Y. Bilgesu, G. Gündüz
Nuclear Technology | Volume 135 | Number 3 | September 2001 | Pages 286-294
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT01-A3223
