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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
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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Hydrogen Production Using High-Temperature Steam Electrolysis Supported by Advanced Gas Reactors with Supercritical CO2 Cycles
Bilge Yildiz, Katherine J. Hohnholt, Mujid S. Kazimi
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 1-21
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3742
Evaluation of the Impact of SAMG on the Level-2 PSA Results of a Pressurized Water Reactor
Yu-Chih Ko, Ching-Hui Wu, Min Lee
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 22-33
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3743
Assessment of a Heterogeneous PWR Assembly for Plutonium and Minor Actinide Recycle
T. A. Taiwo, T. K. Kim, J. A. Stillman, R. N. Hill, M. Salvatores, P. J. Finck
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 34-54
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3744
Evaluation of Long-Life Transuranics Breakeven and Burner Cores for Waste Minimization in a PB-GCFR Fuel Cycle
T. A. Taiwo, E. A. Hoffman, R. N. Hill, W. S. Yang
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 55-66
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3745
Feasibility Study on Transient Identification in Nuclear Power Plants Using Support Vector Machines
Christoffer Gottlieb, Vasily Arzhanov, Waclaw Gudowski, Ninos Garis
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 67-77
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT06-A3746
Investigation of Polonium Decontamination from Stainless Steel Surfaces Using the Baking Method
Terumitsu Miura, Toru Obara, Hiroshi Sekimoto
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 78-89
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT06-A3747
Thermal Design of an Alternative Boiling Water Reactor Spent Nuclear Fuel Package for Yucca Mountain Repository
P. Kar, G. Danko, J. S. Armijo, M. Misra, D. Bahrami
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 90-104
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3748
Chemical Thermodynamics Consideration on Corrosion Products in Supercritical-Water-Cooled Reactor Coolant
Norihisa Saito, Yumiko Tsuchiya, Seiji Yamamoto, Yoshie Akai, Tadasu Yotsuyanagi, Masafumi Domae, Yosuke Katsumura
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 105-113
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3749
Chronic Dose Due to a Continuous Tritium Release Calculated by CAP88-PC and NORMTRI
Stacey F. Imboden, Thomas J. Overcamp
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 114-118
Technical Note | Radiation Protection | doi.org/10.13182/NT06-A3750
Prediction of Corrosion Behavior of HLW Containers in the Framework of the French Interim Storage Concept
M. Hélie, Cl. Desgranges, St. Perrin
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 120-132
Technical Paper | Materials | doi.org/10.13182/NT06-A3751
Development and Testing of an Advanced Neutron-Absorbing Gadolinium Alloy for Spent Nuclear Fuel Storage
Ronald E. Mizia, Tedd E. Lister, Patrick J. Pinhero, Tammy L. Trowbridge, William L. Hurt, Charles V. Robino, John J. Stephens, Jr., John N. DuPont
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 133-148
Technical Paper | Materials | doi.org/10.13182/NT06-A3752
The Accelerated Weathering of a Radioactive Low-Activity Waste Glass Under Hydraulically Unsaturated Conditions: Experimental Results from a Pressurized Unsaturated Flow Test
E. M. Pierce, B. P. McGrail, M. M. Valenta, D. M. Strachan
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 149-165
Technical Paper | Materials | doi.org/10.13182/NT06-A3753
Validating a Monte Carlo Model of the University of Wisconsin Nuclear Reactor with Operational Data
Paul W. Humrickhouse, Paul P. H. Wilson
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 166-175
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3754
Progress of the DUPIC Fuel Compatibility Analysis - III: Reactor Safety
Chang Joon Jeong, Bo Wook Rhee, Hangbok Choi, Myung Seung Yang
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 176-191
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3755
Well-to-Wheels Analysis of Energy Use and Greenhouse Gas Emissions of Hydrogen Produced with Nuclear Energy
Ye Wu, Michael Q. Wang, Anant D. Vyas, David C. Wade, Temitope A. Taiwo
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 192-207
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3756
Colloid-Radionuclide Transport Within Fractured Rock: Potential Impact of Nonlinear Sorption Kinetics
Neng-Chuan Tien, Shih-Hai Li
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 208-225
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3757
Mathematical Analysis on Partitioning and Transmutation System with a Two-Member Nuclide Chain
Joonhong Ahn, Paul L. Chambré, Byung-Hyun Park
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 226-247
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3758
Tritium Measurements in Neutron-Induced Cavitation of Deuterated Acetone
Lefteri Tsoukalas, Franklin Clikeman, Martin Bertodano, Tatjana Jevremovic, Joshua Walter, Anton Bougaev, Edward Merritt
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 248-251
Technical Note | Radiation Measurements and Instrumentation | doi.org/10.13182/NT06-A3759
Development of Drywell Water Level Computational Aid and Application on Containment Flooding Strategy of Mark-III Nuclear Power Plant
Wei-Nian Su, Shih-Jen Wang, I-Ming Huang, Show-Chyuan Chiang
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 253-264
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3760
Full-Height Thermal-Hydraulic Scaling Analysis of Pb-Bi-Cooled Fast Reactor PEACER
Il S. Lee, Kune Y. Suh
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 265-281
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3761
Analysis of Pellet-Clad Mechanical Interaction Process of High-Burnup PWR Fuel Rods by RANNS Code in Reactivity-Initiated Accident Conditions
Motoe Suzuki, Toyoshi Fuketa, Hiroaki Saitou
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 282-292
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3762
An Assessment of Fuel Damage in Postulated Reactivity-Initiated Accidents
Ralph O. Meyer
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 293-311
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3763
A Linear Stability Analysis for Natural-Circulation Loops Under Supercritical Conditions
R. Jain, M. L. Corradini
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 312-323
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3764
Simulant Melt Experiments on In-Vessel Retention Through External Reactor Vessel Cooling
Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, Hee-Dong Kim, Soon-Heung Chang
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 324-339
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3765
A System Design Study of a Fast Breeder Reactor Hydrogen Production Plant Using Thermochemical and Electrolytic Hybrid Process
Yoshitaka Chikazawa, Toshio Nakagiri, Mamoru Konomura, Shouji Uchida, Yoshihiko Tsuchiyama
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 340-349
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3766
A 16N/19O Monitor for Leak Detection in a Steam Generator
Shengyao Ding, Kun Xu, Xiaojian Huang, Zheng Wang
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 350-357
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT06-A3767
Calculation of Corrosion Rates of Alpha-Doped UO2
Hilbert Christensen
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 358-364
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT06-A3768
