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Nuclear Technology
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February 2025
Latest News
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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Gaussian Processes for State Identification in Pressurized Water Reactors
Andreas Ikonomopoulos, Miltiadis Alamaniotis, Stylianos Chatzidakis, Lefteri H. Tsoukalas
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 1-12
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-A15821
Assessment of the Efficiency of Extended Power Uprates at U.S. Boiling Water Reactors
Brenden Heidrich, Samuel A. Oyewole, Richard Olawoyin
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 13-25
Technical Paper | Fission Reactors/Nuclear Plant Operations and Control | doi.org/10.13182/NT13-A15822
Salt-Cooled Modular Innovative Thorium Heavy Water-Moderated Reactor System
Holly R. Trellue, Richard J. Kapernick, D. V. Rao, J. Zhang, Jack D. Galloway
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 26-38
Technical Paper | Fission Reactors/Fuel Cycle and Management | doi.org/10.13182/NT13-A15823
Viability Assessment of Noble Gas Bundle Tagging for Failed-Fuel Identification in CANDU Reactors
B. Pollack, B. J. Lewis, D. Kelly
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 39-48
Technical Paper | Fission Reactors/Fuel Cycle and Management | doi.org/10.13182/NT13-A15824
The Effect of Coating Parameters and Annealing on the Crushing Strength of TRISO Coated Particles
J. J. Hancke, G. T. Van Rooyen, J. P. R. De Villiers
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 49-56
Technical Paper | Fission Reactors/Fuel Cycle and Management | doi.org/10.13182/NT13-A15825
The Role of Gd2O3 Phase Transition on UO2-Gd2O3 Fuel Sintering
Michelangelo Durazzo, Ricardo Mendes Leal Neto, Adonis Marcelo Saliba-Silva, Elita Fontenele Urano de Carvalho, Humberto Gracher Riella
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 57-62
Technical Paper | Fuel Cycle and Management/Miscellaneous | doi.org/10.13182/NT13-A15826
Hybrid Monte Carlo/Deterministic Methods for Accelerating Active Interrogation Modeling
Douglas E. Peplow, Thomas M. Miller, Bruce W. Patton, John C. Wagner
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 63-74
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT13-A15827
Updating of Analytical Model to Consider Aging Effects of Lead-Rubber Bearings for the Seismic Design of Base-Isolated Nuclear Power Plants
Thuy Dung Vu, Dookie Kim, Sung Gook Cho
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 75-83
Technical Paper | Nuclear Plant Operations and Control/Miscellaneous | doi.org/10.13182/NT13-A15828
Single-Stage Dual-Column HPLC Technique for Separation and Determination of Lanthanides in Uranium Matrix: Application to Burnup Measurement on Nuclear Reactor Fuel
Arpita Datta, N. Sivaraman, T. G. Srinivasan, P. R. Vasudeva Rao
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 84-97
Technical Paper | Reprocessing | doi.org/10.13182/NT13-A15829
Modeling the Anodic Behavior of U, Zr, and U-Zr Alloy in Molten LiCl-KCl Eutectic
Aligati Venkatesh, Suddhasattwa Ghosh, S. Vandarkuzhali, B. Prabhakara Reddy, K. Nagarajan, P. R. Vasudeva Rao
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 98-110
Technical Paper | Reprocessing | doi.org/10.13182/NT182-98
Long-Term Electrochemical Criteria for Crevice Corrosion in Concentrated Chloride Solutions
T. Ahn, H. Jung, P. Shukla, X. He
Nuclear Technology | Volume 182 | Number 1 | April 2013 | Pages 111-122
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT13-A15831
Simulation of Pellet-Cladding Interaction with the PLEIADES Fuel Performance Software Environment
B. Michel, C. Nonon, J. Sercombe, F. Michel, V. Marelle
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 124-137
Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fuel Cycle and Management | doi.org/10.13182/NT13-A16424
On the Response of Ionic Crystals to Irradiation
Dilpuneet Aidhy, Dieter Wolf
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 138-144
Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fuel Cycle and Management | doi.org/10.13182/NT13-A16425
Three-Dimensional Characterization of Sintered UO2+x: Effects of Oxygen Content on Microstructure and Its Evolution
Karin Rudman, Patricia Dickerson, Darrin Byler, Robert McDonald, Harn Lim, Pedro Peralta, Chris Stanek, Kenneth McClellan
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 145-154
Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fuel Cycle and Management | doi.org/10.13182/NT13-A16426
Microstructurally Explicit Simulation of Intergranular Mass Transport in Oxide Nuclear Fuels
Harn Chyi Lim, Karin Rudman, Kapil Krishnan, Robert McDonald, Patricia Dickerson, Darrin Byler, Pedro Peralta, Chris Stanek, Kenneth McClellan
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 155-163
Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fuel Cycle and Management | doi.org/10.13182/NT13-A16427
Transmission Electron Microscopy Investigation of Krypton Bubbles in Polycrystalline CeO2
Lingfeng He, Clarissa Yablinsky, Mahima Gupta, Jian Gan, Marquis A. Kirk, Todd R. Allen
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 164-169
Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Materials for Nuclear Systems | doi.org/10.13182/NT13-A16428
R&D in Support of ASTRID and JSFR: Cross-Analysis and Identification of Possible Areas of Cooperation
Nicolas Devictor, Yoshitaka Chikazawa, Manuel Saez, Gilles Rodriguez, Hiroki Hayafune
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 170-186
Regular Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fission Reactors | doi.org/10.13182/NT13-A16429
Introduction of Thorium-Based Fuels in High Conversion Pressurized Water Reactors
V. Vallet, B. Gastaldi, J. Politello, A. Santamarina, L. Van Den Durpel
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 187-206
Regular Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fission Reactors | doi.org/10.13182/NT13-A16430
Determining Optimal Neutron Spectra for Transmutation and Isotope Management
Mark Massie, Benoit Forget
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 207-223
Regular Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fission Reactors | doi.org/10.13182/NT13-A16431
Effects of Source and Geometry Modeling on the Shielding Calculations for a Spent Nuclear Fuel Dry Storage Cask
Y. F. Chen, Y. F. Chiou, S. J. Chang, S. H. Jiang, R. J. Sheu
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 224-234
Regular Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Radiation Transport and Protection | doi.org/10.13182/NT13-A16432
Study on UF-2 Extraction in Accelerator Mass Spectrometry Measurement of 236U
Xianggao Wang, Kejun Dong, Ming He, Shaoyong Wu, Shan Jiang
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 235-241
Regular Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Reprocessing | doi.org/10.13182/NT13-A16433
Laser-Assisted Decontamination of Fuel Pins for Prototype Fast Breeder Reactor
Aniruddha Kumar, R. B. Bhatt, Mohd. Afzal, J. P. Panakkal, Dhruba J. Biswas, J. Padma Nilaya, A. K. Das
Nuclear Technology | Volume 182 | Number 2 | May 2013 | Pages 242-247
Regular Technical Paper | Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Decontamination/Decommissioning | doi.org/10.13182/NT13-A16434
Detection of Simulated Steam Leak into Sodium in Steam Generator of PFBR by Argon Injection Using Signal Analysis Techniques
P. Kalyanasundaram, Baldev Raj, V. Prakash, Ramakrishna Ranga
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 249-258
Technical Paper | Fission Reactors/Nuclear Plant Operations and Control | doi.org/10.13182/NT13-A16977
Experimental Investigation of Hydraulics and Lateral Mixing for Helical-Cruciform Fuel Rod Assemblies
T. M. Conboy, T. J. McKrell, M. S. Kazimi
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 259-273
Technical Paper | Fuel Cycle and Management/Thermal Hydraulics | doi.org/10.13182/NT12-58
Transmutation Fuel Cycle Analyses of the SABR Fission-Fusion Hybrid Burner Reactor for Transuranic and Minor Actinide Fuels
C. M. Sommer, W. M. Stacey, B. Petrovic, C. L. Stewart
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 274-285
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-A16979
A Study of Nanoparticle Surface Modification Effects on Pool Boiling Critical Heat Flux
G. Stange, H. Yeom, B. Semerau, K. Sridharan, M. Corradini
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 286-301
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-A16980
The Triggerability and Explosion Potentials of Reactor Core Melt at Fuel Coolant Interactions
I. K. Park, J. H. Kim, S. H. Hong, S. W. Hong
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 302-314
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-A16981
Thermal-Hydraulic Analysis for HEU and LEU Transitional Core Conversion of the MIT Research Reactor
Sung Joong Kim, Lin-Wen Hu, Floyd Dunn
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 315-334
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-81
Comparison of Measured and Monte Carlo Results for Neutron Beam Transmission Through an Irradiated Nuclear Fuel Assembly
Chad L. Pope, Michael J. Lineberry
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 335-348
Technical Paper | Radiation Transport and Protection/Radioisotopes | doi.org/10.13182/NT13-A16983
Application of Zirconium Alloys for Reprocessing Plant Components
U. Kamachi Mudali, A. Ravi Shankar, R. Natarajan, N. Saibaba, Baldev Raj
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 349-357
Technical Paper | Reprocessing/Materials for Nuclear Systems | doi.org/10.13182/NT12-73
Intelligent Radioactive Waste Management Platform for Radioactive Waste Storage Facilities
Y.-C. Chen, Y.-S. Yu, R.-S. Chen, I-Hsin Chou, H. M. Sun, K. C. Yeh
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 358-368
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT13-A16985
Analysis of Measurement Uncertainty of Material Unaccounted for in the Reference Pyroprocessing Facility
Bo-Young Han, Hee-Sung Shin, Ho-Dong Kim
Nuclear Technology | Volume 182 | Number 3 | June 2013 | Pages 369-377
Technical Note | Fuel Cycle and Management | doi.org/10.13182/NT13-A16986
