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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Judge temporarily blocks DOE’s move to slash university research funding
A group of universities led by the American Association of Universities (AAU) acted swiftly to oppose a policy action by the Department of Energy that would cut the funds it pays to universities for the indirect costs of research under DOE grants. The group filed suit Monday, April 14, challenging a what it termed a “flagrantly unlawful action” that could “devastate scientific research at America’s universities.”
By Wednesday, the U.S. District Court judge hearing the case issued a temporary restraining order effective nationwide, preventing the DOE from implementing the policy or terminating any existing grants.
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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
