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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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Application of the Pitzer Method for Modeling Densities of Actinide Solutions in the SCALE Code System
Charles F. Weber, Calvin M. Hopper
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 1-8
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3684
A Methodology for Developing a Probability Distribution for the Failure Enthalpy of High-Burnup Fuels via Simulation
Lorenzo P. Pagani, George E. Apostolakis
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 9-17
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3685
Fission Gas Release from Uranium-Zirconium Hydride Fuel During Heating to Melting
Yeon Soo Kim, Gerard L. Hofman, James L. Snelgrove
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 18-24
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3686
Progress of the DUPIC Fuel Compatibility Analysis - I: Reactor Physics
Hangbok Choi, Chang Joon Jeong, Gyu Hong Roh, Bo Wook Rhee, Myung Seung Yang
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 25-40
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3687
A Conservative Analysis Methodology for a Steam-Line-Break Accident of the SMART-P Plant
Young-Jong Chung, Hee-Kyung Kim, Hee-Cheol Kim, Sung-Quun Zee
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 41-52
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3688
A Generic Method to Evaluate the Reasonable Upper-Bound Dose from Near-Surface Radioactive Waste Disposal Facilities Through Drinking Water Pathway
R. N. Nair, Y. S. Mayya, V. D. Puranik
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 53-69
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3689
Extracting Risk Insights from Performance Assessments for High-Level Radioactive Waste Repositories
S.Tina Ghosh, George E. Apostolakis
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 70-88
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3690
The Applicability of a Quenching Mesh as a Hydrogen Flame Arrester in Nuclear Power Plants
Seong-Wan Hong, Jin-Ho Song, Hee-Dong Kim, Soon-Heung Chang
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 89-99
Technical Paper | Miscellaneous | doi.org/10.13182/NT06-A3691
Development of Control Technology for the HTTR Hydrogen Production System
Tetsuo Nishihara, Yoshiyuki Inagaki
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 100-106
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT06-A3692
Alpha-Particle Low-Level Waste Control: Improvement of the PROMETHEE 6 Assay System Performances
Fanny Jallu, Alain Mariani, Christian Passard, Anne-Cecile Raoux, Herve Toubon
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 107-115
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3693
On an Improved Design of a Fluidized Bed Nuclear Reactor - I: Design Modifications and Steady-State Features
Alexander Agung, Danny Lathouwers, Tim H. J. J. van der Hagen, Hugo van Dam, Christopher C. Pain, Anthony J. H. Goddard, Matthew D. Eaton, Jefferson L. M. A. Gomes, Bryan Miles, Cassiano R. E. de Oliveira
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 117-131
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3694
A Physics Study on Thorium Fuel Recycling in a CANDU Reactor Using Dry Process Technology
Hangbok Choi, Chang Je Park
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 132-145
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3695
Recycle of Transuranium Elements in Light Water Reactors for Reduction of Geological Storage Requirements
E. Fridman, E. Shwageraus, A. Galperin, M. Todosow
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 146-163
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3696
Progress of the DUPIC Fuel Compatibility Analysis - II: Thermal Hydraulics
Joo Hwan Park, Jee-Won Park, Hangbok Choi, Myung Seung Yang
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 164-174
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3697
Experiment and RELAP5 Analysis for the Downcomer Boiling of APR1400 Under LBLOCA Reflood Phase
Dong Won Lee, Hee Cheon No, Eu Hwak Lee, Seung Jong Oh, Chul-Hwa Song
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 175-183
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3698
Modeling of a Power Conversion System with RELAP5-3D/K and Associated Application to the Feedwater Blowdown Licensing Analysis for the ABWR Containment Design
Thomas K. S. Liang, Chung-Yu Yang, Liang-Che Dai, Fu-Kuang Ko
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 184-196
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3699
Computational Fluid Dynamics Predicting the Distributions of Thinning Locations on the Shell Wall of Feedwater Heaters
Y.-M. Ferng, J. H. Hsieh, C. D. Horng
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 197-207
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3700
Simulant Melt Experiments on Thermal and Metallurgical Performance of the In-Vessel Core Catcher
Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, K.Y. Suh, F. B. Cheung, J. L. Rempe
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 208-223
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3701
Breeding of 242mAm in a Fast Reactor
Y. Ronen, M. Aboudy, D. Regev
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 224-233
Technical Note | Fuel Cycle and Management | doi.org/10.13182/NT06-A3702
The Temperature Feature on the Step-Up Process of the Hydraulic Control Rod Driving System
Yanhua Zheng, Hanliang Bo, Duo Dong
Nuclear Technology | Volume 153 | Number 2 | February 2006 | Pages 234-239
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT06-A3703
The Development of SIMMER-III, An Advanced Computer Program for LMFR Safety Analysis, and Its Application to Sodium Experiments
Y. Tobita, Sa. Kondo, H. Yamano, K. Morita, W. Maschek, P. Coste, T. Cadiou
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 245-255
Technical Paper | Sodium Technology - Thermal Hydraulics | doi.org/10.13182/NT06-2
Evaluation of the Accident Scenario Initiated by a Total Instantaneous Blockage in a Phénix Subassembly
Thierry Cadiou, Jacky Louvet
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 256-263
Technical Paper | Sodium Technology - Reactor Safety | doi.org/10.13182/NT06-A3705
Contribution of Phénix to the Development of Transmutation Fuels and Targets in Sodium Fast Breeder Reactors
S. Pillon, F. Sudreau, G. Gaillard-Groléas
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 264-273
Technical Paper | Sodium Technology - Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3706
Phénix Steam Generator Module Repair: Sodium Removal Process, Ultrasonic Controls, and Repair Method
Ch. Cavagna, O. Gastaldi, L. Martin, V. Grabon
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 274-281
Technical Note | Sodium Technology - Thermal Hydraulics | doi.org/10.13182/NT06-A3707
Study of Solid Moderators for the Thermal-Spectrum Supercritical Water-Cooled Reactor
Jacopo Buongiorno, James W. Sterbentz, Philip E. MacDonald
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 282-303
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3708
Root Cause of Instability in Liquid Zone Control System of CANDU Reactor
Sang-Nyung Kim, Byung-Marn Koh, Joon-Suk Ji
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 304-314
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3709
Consequences of Different Types of Contact Between Water and Molten Steel: The ANAIS Experiments
Michel Amblard, Jean-Marc Delhaye, Karine Froment, Jean-Marie Seiler, Bruno Tourniaire
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 315-325
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3710
Robust Dynamic Sensor Fault Detection and Isolation of Helical Coil Steam Generator Systems Using a Subspace Identification Technique
Ke Zhao, Belle R. Upadhyaya, Richard T. Wood
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 326-340
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT06-A3711
Phenomenology of Baneberry Nuclear Event Revisited with 3-D Finite Element Transient Simulation
Rajeev Ranjan, R. K. Singh, S. K. Sikka, Anil Kakodkar
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 341-359
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3712
Evaluation of the Efficiency of Gamma Spectrometers for Analyzing Environmental Samples with Unknown Elemental Composition
Nader M. A. Mohamed, M. Abou Mandour, M. K. Shaat, Alya A. Badawi
Nuclear Technology | Volume 153 | Number 3 | March 2006 | Pages 360-364
Technical Note | Radiation Measurements and Instrumentation | doi.org/10.13182/NT06-A3713
