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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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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Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
NRC issues subsequent license renewal to Monticello plant
The Nuclear Regulatory Commission has renewed for a second time the operating license for Unit 1 of Minnesota’s Monticello nuclear power plant.
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Hydrogen Production Using High-Temperature Steam Electrolysis Supported by Advanced Gas Reactors with Supercritical CO2 Cycles
Bilge Yildiz, Katherine J. Hohnholt, Mujid S. Kazimi
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 1-21
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3742
Evaluation of the Impact of SAMG on the Level-2 PSA Results of a Pressurized Water Reactor
Yu-Chih Ko, Ching-Hui Wu, Min Lee
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 22-33
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3743
Assessment of a Heterogeneous PWR Assembly for Plutonium and Minor Actinide Recycle
T. A. Taiwo, T. K. Kim, J. A. Stillman, R. N. Hill, M. Salvatores, P. J. Finck
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 34-54
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3744
Evaluation of Long-Life Transuranics Breakeven and Burner Cores for Waste Minimization in a PB-GCFR Fuel Cycle
T. A. Taiwo, E. A. Hoffman, R. N. Hill, W. S. Yang
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 55-66
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3745
Feasibility Study on Transient Identification in Nuclear Power Plants Using Support Vector Machines
Christoffer Gottlieb, Vasily Arzhanov, Waclaw Gudowski, Ninos Garis
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 67-77
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT06-A3746
Investigation of Polonium Decontamination from Stainless Steel Surfaces Using the Baking Method
Terumitsu Miura, Toru Obara, Hiroshi Sekimoto
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 78-89
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT06-A3747
Thermal Design of an Alternative Boiling Water Reactor Spent Nuclear Fuel Package for Yucca Mountain Repository
P. Kar, G. Danko, J. S. Armijo, M. Misra, D. Bahrami
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 90-104
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3748
Chemical Thermodynamics Consideration on Corrosion Products in Supercritical-Water-Cooled Reactor Coolant
Norihisa Saito, Yumiko Tsuchiya, Seiji Yamamoto, Yoshie Akai, Tadasu Yotsuyanagi, Masafumi Domae, Yosuke Katsumura
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 105-113
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3749
Chronic Dose Due to a Continuous Tritium Release Calculated by CAP88-PC and NORMTRI
Stacey F. Imboden, Thomas J. Overcamp
Nuclear Technology | Volume 155 | Number 1 | July 2006 | Pages 114-118
Technical Note | Radiation Protection | doi.org/10.13182/NT06-A3750
Prediction of Corrosion Behavior of HLW Containers in the Framework of the French Interim Storage Concept
M. Hélie, Cl. Desgranges, St. Perrin
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 120-132
Technical Paper | Materials | doi.org/10.13182/NT06-A3751
Development and Testing of an Advanced Neutron-Absorbing Gadolinium Alloy for Spent Nuclear Fuel Storage
Ronald E. Mizia, Tedd E. Lister, Patrick J. Pinhero, Tammy L. Trowbridge, William L. Hurt, Charles V. Robino, John J. Stephens, Jr., John N. DuPont
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 133-148
Technical Paper | Materials | doi.org/10.13182/NT06-A3752
The Accelerated Weathering of a Radioactive Low-Activity Waste Glass Under Hydraulically Unsaturated Conditions: Experimental Results from a Pressurized Unsaturated Flow Test
E. M. Pierce, B. P. McGrail, M. M. Valenta, D. M. Strachan
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 149-165
Technical Paper | Materials | doi.org/10.13182/NT06-A3753
Validating a Monte Carlo Model of the University of Wisconsin Nuclear Reactor with Operational Data
Paul W. Humrickhouse, Paul P. H. Wilson
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 166-175
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3754
Progress of the DUPIC Fuel Compatibility Analysis - III: Reactor Safety
Chang Joon Jeong, Bo Wook Rhee, Hangbok Choi, Myung Seung Yang
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 176-191
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3755
Well-to-Wheels Analysis of Energy Use and Greenhouse Gas Emissions of Hydrogen Produced with Nuclear Energy
Ye Wu, Michael Q. Wang, Anant D. Vyas, David C. Wade, Temitope A. Taiwo
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 192-207
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3756
Colloid-Radionuclide Transport Within Fractured Rock: Potential Impact of Nonlinear Sorption Kinetics
Neng-Chuan Tien, Shih-Hai Li
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 208-225
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3757
Mathematical Analysis on Partitioning and Transmutation System with a Two-Member Nuclide Chain
Joonhong Ahn, Paul L. Chambré, Byung-Hyun Park
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 226-247
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3758
Tritium Measurements in Neutron-Induced Cavitation of Deuterated Acetone
Lefteri Tsoukalas, Franklin Clikeman, Martin Bertodano, Tatjana Jevremovic, Joshua Walter, Anton Bougaev, Edward Merritt
Nuclear Technology | Volume 155 | Number 2 | August 2006 | Pages 248-251
Technical Note | Radiation Measurements and Instrumentation | doi.org/10.13182/NT06-A3759
Development of Drywell Water Level Computational Aid and Application on Containment Flooding Strategy of Mark-III Nuclear Power Plant
Wei-Nian Su, Shih-Jen Wang, I-Ming Huang, Show-Chyuan Chiang
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 253-264
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3760
Full-Height Thermal-Hydraulic Scaling Analysis of Pb-Bi-Cooled Fast Reactor PEACER
Il S. Lee, Kune Y. Suh
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 265-281
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3761
Analysis of Pellet-Clad Mechanical Interaction Process of High-Burnup PWR Fuel Rods by RANNS Code in Reactivity-Initiated Accident Conditions
Motoe Suzuki, Toyoshi Fuketa, Hiroaki Saitou
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 282-292
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3762
An Assessment of Fuel Damage in Postulated Reactivity-Initiated Accidents
Ralph O. Meyer
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 293-311
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3763
A Linear Stability Analysis for Natural-Circulation Loops Under Supercritical Conditions
R. Jain, M. L. Corradini
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 312-323
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3764
Simulant Melt Experiments on In-Vessel Retention Through External Reactor Vessel Cooling
Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, Hee-Dong Kim, Soon-Heung Chang
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 324-339
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3765
A System Design Study of a Fast Breeder Reactor Hydrogen Production Plant Using Thermochemical and Electrolytic Hybrid Process
Yoshitaka Chikazawa, Toshio Nakagiri, Mamoru Konomura, Shouji Uchida, Yoshihiko Tsuchiyama
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 340-349
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3766
A 16N/19O Monitor for Leak Detection in a Steam Generator
Shengyao Ding, Kun Xu, Xiaojian Huang, Zheng Wang
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 350-357
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT06-A3767
Calculation of Corrosion Rates of Alpha-Doped UO2
Hilbert Christensen
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 358-364
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT06-A3768
