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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
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!
Latest Magazine Issues
Feb 2025
Jul 2024
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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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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
