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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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!
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The deadline is fast approaching for submitting an application to become a technical reviewer for the Nuclear Regulatory Commission’s fiscal year 2025 research grant proposals.
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ATBR - A Thorium Breeder Reactor Concept for Early Induction of Thorium in an Enriched Uranium Reactor
V. Jagannathan, Usha Pal, R. Karthikeyan, S. Ganesan, R. P. Jain, S. U. Kamat
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 1-32
Technical Paper | Fission Reactors | doi.org/10.13182/NT01-A3156
Kinetics of Gaseous Iodine Uptake onto Stainless Steel During Iodine-Assisted Corrosion
Jungsook Clara Wren, Glenn A. Glowa
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 33-49
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3157
Behavior of High-Burnup PWR Fuels with Low-Tin Zircaloy-4 Cladding Under Reactivity-Initiated-Accident Conditions
Toyoshi Fuketa, Hideo Sasajima, Tomoyuki Sugiyama
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 50-62
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3158
Experimental Investigation of Mixing Phenomena Inside a Concrete Containment Cooled by an Innovative Passive System
Luigi Brusa, Alessandro Bianchi, Giancarlo Fruttuoso, Antonio Manfredini, Francesco Oriolo, Mario D. Carelli, Robert P. Kendig, Fred E. Peters
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 63-76
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3159
Investigation of Core Thermohydraulics in Fast Reactors - Interwrapper Flow During Natural Circulation
H. Kamide, K. Hayashi, T. Isozaki, M. Nishimura
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 77-91
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3160
Evaluation of Impurity Behavior in the Reactor Water of a Boiling Water Reactor
Hiroo Igarashi, Nobuyuki Ohta, Naoshi Usui, Katsumi Ohsumi, Shunsuke Uchida, Tsuneo Matsui
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 92-102
Technical Paper | Nuclear Plant Operation and Control | doi.org/10.13182/NT01-A3161
Removal of Zirconium in Electrometallurgical Treatment of Experimental Breeder Reactor II Spent Fuel
Rajesh K. Ahluwalia, Thanh Q. Hua, Howard K. Geyer
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 103-118
Technical Paper | Reprocessing | doi.org/10.13182/NT01-A3162
Neutron Radiography Flow Visualization of Liquid Metal Injected into an Empty Vessel and a Vessel Containing Saturated Water
Yasuteru Sibamoto, Hideo Nakamura, Yoshinari Anoda
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 119-132
Technical Paper | Radioisotopes | doi.org/10.13182/NT01-A3163
Assessment of TRAC-BF1 for Waterhammer Calculations with Entrapped Air
Kevin W. Brinckman, Mark A. Chaiko
Nuclear Technology | Volume 133 | Number 1 | January 2001 | Pages 133-139
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT01-A3164
Development of a Simulation Model and Safety Evaluation for a Depressurization Accident Without Reactor Scram in an Advanced HTGR
Shigeaki Nakagawa, Akio Saikusa, Kazuhiko Kunitomi
Nuclear Technology | Volume 133 | Number 2 | February 2001 | Pages 141-152
Technical Paper | Fission Reactors | doi.org/10.13182/NT01-A3165
PLUTON: A Three-Group Model for the Radial Distribution of Plutonium, Burnup, and Power Profiles in Highly Irradiated LWR Fuel Rods
Sergei Lemehov, Jinichi Nakamura, Motoe Suzuki
Nuclear Technology | Volume 133 | Number 2 | February 2001 | Pages 153-168
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3166
Multidimensional TMI-1 Main-Steam-Line-Break Analysis Methodology Using TRAC-PF/NEM
Kostadin N. Ivanov, Tara M. Beam, Anthony J. Baratta, Ardesar Irani, Nicholas G. Trikouros
Nuclear Technology | Volume 133 | Number 2 | February 2001 | Pages 169-186
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3167
Assessment of the ATHENA Code for Calculating the Void Fraction of a Lead-Bismuth/Steam Mixture in Vertical Upflow
Cliff B. Davis
Nuclear Technology | Volume 133 | Number 2 | February 2001 | Pages 187-193
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3168
Corium Oxidation at Temperatures Above 2000 K
Donald L. Hagrman, Joy L. Rempe
Nuclear Technology | Volume 133 | Number 2 | February 2001 | Pages 194-212
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3169
Neural Network with Local Memory for Nuclear Reactor Power Level Control
Önder Uluyol, Magdi Ragheb, Lefteri Tsoukalas
Nuclear Technology | Volume 133 | Number 2 | February 2001 | Pages 213-228
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT01-A3170
Transmutation of Elemental Cesium by a Fusion Neutron Source
Masaki Saito, Vladimir A. Apse, Vladimir V. Artisyuk, Anatolii N. Chmelev
Nuclear Technology | Volume 133 | Number 2 | February 2001 | Pages 229-241
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-A3171
Concepts in Waste Management: Cerium-Promoted Dissolution of Refractory Actinide Oxides
Daniel William Tedder, Bruce C. Finney
Nuclear Technology | Volume 133 | Number 2 | February 2001 | Pages 242-252
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-A3172
Modeling of Hydrodynamic Chromatography for Colloid Migration in Fractured Rock
Shih-Hai Li, Chun-Ping Jen
Nuclear Technology | Volume 133 | Number 2 | February 2001 | Pages 253-263
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-A3173
Application of the Integrated TH-PA Method to the Westinghouse AP600 Design
Yue Guan, Fei Li, Mohammad Modarres, David Bessette, Marino Dimarzo
Nuclear Technology | Volume 133 | Number 3 | March 2001 | Pages 269-289
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3174
A Method of Integrating Thermal-Hydraulic Analysis and Probabilistic Assessment for Safety Evaluation and Screening
Yue Guan, Fei Li, Mohammad Modarres
Nuclear Technology | Volume 133 | Number 3 | March 2001 | Pages 290-309
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3175
Performance of Near-Weapons-Grade Plutonium Fuel Pins in Commercial Light Water Reactors
Felix C. Difilippo, Stephen E. Fisher
Nuclear Technology | Volume 133 | Number 3 | March 2001 | Pages 310-324
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3176
A Modification of the Inner and Outer Core for Reactor Pressure Vessel Lifetime Extension
Bo Kyun Seo, Jong Kyung Kim, Chang Ho Shin, Tae Je Kwon
Nuclear Technology | Volume 133 | Number 3 | March 2001 | Pages 325-337
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3177
Prediction of a Breakthrough Curve of Iodine on a Reduced Silver-Loaded Adsorbent Bed
Kenji Takeshita, Yoshio Nakano
Nuclear Technology | Volume 133 | Number 3 | March 2001 | Pages 338-345
Technical Paper | Reprocessing | doi.org/10.13182/NT01-A3178
Generation, Testing, and Validation of a WIMS-D/4 Multigroup Cross-Section Library Based on the JENDL-3.2 Nuclear Data
Mafizur Rahman, Hideki Takano
Nuclear Technology | Volume 133 | Number 3 | March 2001 | Pages 346-354
Technical Note | Fission Reactors | doi.org/10.13182/NT01-A3179
Development Program of LOCA Licensing Calculation Capability with RELAP5-3D in Accordance with Appendix K of 10 CFR 50.46
Thomas K. S. Liang, Richard R. Schultz
Nuclear Technology | Volume 133 | Number 3 | March 2001 | Pages 355-358
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT01-A3180
