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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Monte Carlo Simulation of the LEU-Fueled SLOWPOKE-2 Nuclear Reactor Using MCNP 4A
Martin J. R. Pierre, Hugues W. Bonin
Nuclear Technology | Volume 125 | Number 1 | January 1999 | Pages 1-12
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2928
Modeling the Removal and Retention of Radioiodine by TEDA-Impregnated Charcoal Under Reactor Accident Conditions
Jungsook Clara Wren, Will Long, Chris J. Moore, Keith R. Weaver
Nuclear Technology | Volume 125 | Number 1 | January 1999 | Pages 13-27
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2929
Methyl Iodide Trapping Efficiency of Aged Charcoal Samples from Bruce-A Emergency Filtered Air Discharge Systems
Jungsook Clara Wren, Chris J. Moore, Miyoko Tateishi Rasmussen, Keith R. Weaver
Nuclear Technology | Volume 125 | Number 1 | January 1999 | Pages 28-39
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2930
Generation of Void in a Molten-Metal Bath by Gas Injection from Below
Michael C. Baker, Riccardo Bonazza
Nuclear Technology | Volume 125 | Number 1 | January 1999 | Pages 40-51
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A2931
Experiments on Pool Boiling of Water from Downward-Facing Hemispheres
Mohamed S. El-Genk, Cheng Gao
Nuclear Technology | Volume 125 | Number 1 | January 1999 | Pages 52-69
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A2932
Optimal Fuzzy Control Design Using Simulated Annealing and Application to Feedwater Heater Control
Kadir Kavaklioglu, Belle R. Upadhyaya
Nuclear Technology | Volume 125 | Number 1 | January 1999 | Pages 70-84
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT99-A2933
Vitrification of Borate Waste Generated by Nuclear Power Plants
Jiawei Sheng, Shanggeng Luo, Baolong Tang
Nuclear Technology | Volume 125 | Number 1 | January 1999 | Pages 85-92
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT99-A2934
A Novel Waste Form for Disposal of Spent-Nuclear-Fuel Reprocessing Waste: A Vitrifiable Cement
Mary Lou Dunzik Gougar, Barry E. Scheetz, Darryl D. Siemer
Nuclear Technology | Volume 125 | Number 1 | January 1999 | Pages 93-103
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT99-A2935
Target and Filter Concepts for Accelerator-Driven Boron Neutron Capture Therapy Applications
James R. Powell, Hans Ludewig, Michael Todosow, Morris Reich
Nuclear Technology | Volume 125 | Number 1 | January 1999 | Pages 104-115
Technical Paper | Accelerators | doi.org/10.13182/NT99-A2936
Detailed Assessment of the Heiss Dampf Reaktor Hydrogen-Mixing Experiments E11
Lothar Wolf, Helmut Holzbauer, Thomas Cron
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 119-135
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2937
Detailed Assessment of the Heiss Dampf Reaktor Hydrogen Deflagration Experiments E12
Lothar Wolf, Ashok Rastogi, Dag Wennerberg, Thomas Cron, Edgar Hansjosten
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 136-154
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2938
Comparisons Between Multidimensional and Lumped-Parameter GOTHIC Containment Analyses with Data
Lothar Wolf, Helmut Holzbauer, Manfred Schall
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 155-165
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2939
GOTHIC Verification on Behalf of the Heiss Dampf Reaktor Hydrogen-Mixing Experiments
Helmut Holzbauer, Lothar Wolf
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 166-181
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2940
Benchmark of the Heiss Dampf Reaktor E11.2 Containment Hydrogen-Mixing Experiment Using the MAAP4 Code
Sung Jin Lee, Chan Y. Paik, Robert E. Henry, Michael Epstein, Martin G. Plys
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 182-196
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A2941
CANDU Reactor Simulations Using the Feedback Model with Actinide Burnup History
Mohamed Tahar Sissaoui, Guy Marleau, Daniel Rozon
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 197-212
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2942
Visualization of Simulated Molten-Fuel Behavior in a Pressure Vessel Lower Head Using High-Frame-Rate Neutron Radiography
Hideo Nakamura, Yasuteru Sibamoto, Yoshinari Anoda, Yutaka Kukita, Kaichiro Mishima, Takashi Hibiki
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 213-224
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A2943
Wavelet Application in Process Monitoring
Andreas Ikonomopoulos, Akira Endou
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 225-234
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT99-A2944
Effects of Perched Water on Thermally Driven Moisture Flow at the Proposed Yucca Mountain Repository for High-Level Waste
Goodluck I. Ofoegbu, Amvrossios C. Bagtzoglou, Ronald T. Green, Michael A. Muller
Nuclear Technology | Volume 125 | Number 2 | February 1999 | Pages 235-253
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT99-A2945
Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel - I: Methodology Overview
Dale B. Lancaster, Emilio Fuentes, Chi H. Kang, Meraj Rahimi
Nuclear Technology | Volume 125 | Number 3 | March 1999 | Pages 255-270
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2946
Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel - II: Validation
Emilio Fuentes, Dale B. Lancaster, Meraj Rahimi
Nuclear Technology | Volume 125 | Number 3 | March 1999 | Pages 271-291
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2947
Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel - III: Bounding Treatment of Spatial Burnup Distributions
Chi H. Kang, Dale B. Lancaster
Nuclear Technology | Volume 125 | Number 3 | March 1999 | Pages 292-304
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2948
Experimental and Computational Study of the Core Inlet Temperature Pattern Under Asymmetric Loop Conditions
Kil-Sup Um, Seok-Hee Ryu, Yong-Seog Choi, Goon-Cherl Park
Nuclear Technology | Volume 125 | Number 3 | March 1999 | Pages 305-315
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A2949
Effects of Magnesium and Zinc Additives on Corrosion and Cobalt Contamination of Stainless Steels in Simulated BWR Coolant
D. H. Lister, G. Venkateswaran
Nuclear Technology | Volume 125 | Number 3 | March 1999 | Pages 316-331
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT99-A2950
Influence of Increased Temperature from Cement Hydration on Aluminum Corrosion Prevention When LiNO3 is Added to the Cement
Toshiaki Matsuo, Takashi Nishi, Tatsuo Izumida, Masami Matsuda
Nuclear Technology | Volume 125 | Number 3 | March 1999 | Pages 332-336
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT99-A2951
The Interaction of Iodine with Organic Material in Containment
Jungsook Clara Wren, Joanne M. Ball, Glenn A. Glowa
Nuclear Technology | Volume 125 | Number 3 | March 1999 | Pages 337-362
Technical Paper | Radioisotopes | doi.org/10.13182/NT99-A2952
Large-Scale Experiments on Ex-Vessel Core Melt Behavior
Manfred Sappok, Wolfgang Steinwarz
Nuclear Technology | Volume 125 | Number 3 | March 1999 | Pages 363-370
Technical Note | Reactor Safety | doi.org/10.13182/NT99-A2953
