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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!
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Feb 2025
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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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Investigations of Hydraulic Behavior in Spallation Target Configurations
Xu Cheng, Abdalla Batta, Nam-Il Tak
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 1-12
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3714
Internal Vessel Cooling Feasibility Attributed by Critical Heat Flux in Inclined Rectangular Gap
Yong H. Kim, Sung J. Kim, Kune Y. Suh, Joy L. Rempe, F. Bill Cheung, Sang B. Kim
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 13-40
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3715
Neutronic and Safety Aspects of a Gas-Cooled Subcritical Core for Minor Actinide Transmutation
Daniel Westlén, Janne Wallenius
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 41-51
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3716
Subchannel Analysis of Fuel Assemblies of European Experimental ADS
X. Cheng
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 52-68
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3717
Accumulation and Head-Loss Characteristics of Selected Pressurized Water Reactor LOCA-Generated Debris
Ashok K. Ghosh, Arup K. Maji, Mark T. Leonard, Dasari V. Rao, Bruce C. Letellier, Girum S. Urgessa, Scott G. Ashbaugh
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 69-84
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3718
Aerosol Retention Near the Tube Breach During Steam Generator Tube Rupture Sequences
Luis E. Herranz, F. J. S. Velasco, Claudia L. Del Prá
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 85-94
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT06-A3719
Separations and Transmutation Criteria to Improve Utilization of a Geologic Repository
Roald A. Wigeland, Theodore H. Bauer, Thomas H. Fanning, Edgar E. Morris
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 95-106
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-3
Results of the QUENCH-09 Experiment Compared to QUENCH-07 with Incorporation of B4C Absorber
L. Sepold, G. Schanz, M. Steinbrück, J. Stuckert, A. Miassoedov, A. Palagin, M. Veshchunov
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 107-116
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT06-A3721
Measurements of Delayed Fission Product Gamma-Ray Transmission Through Low-Enriched UO2 Fuel Pin Lattices in Air
T. H. Trumbull, D. R. Harris
Nuclear Technology | Volume 154 | Number 1 | April 2006 | Pages 117-127
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT06-A3722
Calculation of the Neutron Noise Induced by Shell-Mode Core-Barrel Vibrations in a 1-D, Two-Group, Two-Region Slab Reactor Model
Carl Sunde, Christophe Demazière, Imre Pázsit
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 129-141
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-1
A Conceptual Design Study of a Small Natural Convection Lead-Bismuth-Cooled Reactor Without Refueling for 30 Years
Yoshitaka Chikazawa, Mamoru Konomura, Tomoyasu Mizuno, Makoto Mito, Mikio Tanji
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 142-154
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3724
Formulation of a Single Operational Model for Risk-Informed Applications from the Decoupled Levels 1 and 2 PSA Models
Kwang-Il Ahn, Joon-Eon Yang
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 155-169
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3725
Mass Transfer Modeling With and Without Evaporation for Iodine Chemistry in the Case of a Severe Accident
L. Cantrel, P. March
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 170-185
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3726
MOX Fuel Characterization for Burnup Credit Application: Extension of Nondestructive Method Qualified for LEU Fuels
C. Riffard, H. Toubon, S. Pelletier, M. Batifol, J. M. Vidal
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 186-193
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3727
Modeling of Radiative Heat Transfer During a PWR Severe Accident
M. Zabiégo, F. Fichot, P. Rubiolo
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 194-214
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3728
The Core Characteristics of a LOCA Power Pulse in a CANDU-6 Reactor with the CANFLEX-RU Fuel
Chang Joon Jeong, Ho Chun Suk
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 215-223
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3729
Continuous Monitoring and Calibration of UTSG Process Sensors by Autoassociative Artificial Neural Network
Marzio Marseguerra, Enrico Zio, Fabio Marcucci
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 224-236
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT06-A3730
Conditions Conducive to Forming Crystalline Uranyl Silicates in High Caustic Nuclear Waste Evaporators
Lawrence N. Oji, Keisha B. Martin, Mary E. Stallings, Martine C. Duff
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 237-246
Technical Paper | Reprocessing | doi.org/10.13182/NT06-A3731
Thermal-Hydrologic Model Study for an Alternative Waste Package Design for Yucca Mountain Repository
D. Bahrami, G. Danko
Nuclear Technology | Volume 154 | Number 2 | May 2006 | Pages 247-264
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3732
High-Performance Supercritical Carbon Dioxide Cycle for Next-Generation Nuclear Reactors
Vaclav Dostal, Pavel Hejzlar, Michael J. Driscoll
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 265-282
Technical Paper | Fission Reactors | doi.org/10.13182/NT154-265
The Supercritical Carbon Dioxide Power Cycle: Comparison to Other Advanced Power Cycles
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 283-301
Technical Paper | Fission Reactors | doi.org/10.13182/NT06-A3734
Behavior of VVER Fuel Rods Tested Under Severe Accident Conditions in the CODEX Facility
Zoltán Hózer, László Maróti, Péter Windberg, Lajos Matus, Imre Nagy, György Gyenes, Márta Horváth, Anna Pintér, Márton Balaskó, Aladár Czitrovszky, Péter Jani, Attila Nagy, Oleg Prokopiev, Béla Tóth
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 302-317
Technical Paper | Reactor Safety | doi.org/10.13182/NT06-A3735
Reduction in Workload of BWR In-Core Fuel Shuffling by New Optimization Methods
Akio Yamamoto, Masayuki Toujou, Kentarou Komori, Yasunori Kitamura, Yoshihiro Yamane
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 318-327
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3736
Analysis of the Bubbly-Churn Regime Transition in a Scaled Model Boiling Water Reactor
Khaled Meftah, Arthur E. Ruggles
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 328-334
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3737
Heat Transfer in a Supercritical Fluid: Classification of Heat Transfer Regimes
Kyoung Woo Seo, Moo Hwan Kim, Mark H. Anderson, Michael L. Corradini
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 335-349
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT06-A3738
The Effect of Material Homogenization in Calculating the Gamma-Ray Dose from Spent PWR Fuel Pins in an Air Medium
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 350-360
Technical Paper | Radiation Protection | doi.org/10.13182/NT06-A3739
Proliferation-Resistant SIGMA Uranium Enrichment Plants
M. E. Rivarola, P. C. Florido, D. O. Brasnarof, K. H. Kyung, L. Juanicó, J. Bergallo, J. Gonzalez, H. Daverio
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 361-373
Technical Paper | Enrichment | doi.org/10.13182/NT06-A3740
Deterministic Performance Assessment for a Conceptual Repository for Low- and Intermediate-Level Wastes in Korea
Daisuke Kawasaki, Joonhong Ahn, Chang-Lak Kim, Jin-Beak Park
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 374-388
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3741
