ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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!
Latest Magazine Issues
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
2024: The Year in Nuclear—April through June
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from April through May 2024.
Stay tuned for the top stories from the rest of the past year.
Jump to:
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
