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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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The SABrR Concept for A Fission-Fusion Hybrid 238U-to-239Pu Fissile Production Reactor
C. L. Stewart, W. M. Stacey
Nuclear Technology | Volume 187 | Number 1 | July 2014 | Pages 1-14
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-102
Resolution of Fission and Fusion Technology Integration Issues: An Upgraded Design Concept for the Subcritical Advanced Burner Reactor
W. M. Stacey, C. L. Stewart, J.-P. Floyd, T. M. Wilks, A. P. Moore, A. T. Bopp, M. D. Hill, S. Tandon, and A. S. Erickson
Nuclear Technology | Volume 187 | Number 1 | July 2014 | Pages 15-43
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-96
Effects of Shape and Size on Countercurrent Flow Limitation in Flow Channels Simulating A PWR Hot Leg
Ikuo Kinoshita, Michio Murase, Yoichi Utanohara, Dirk Lucas, Christophe Vallée, and Akio Tomiyama
Nuclear Technology | Volume 187 | Number 1 | July 2014 | Pages 44-56
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-32
Clogging of HEPA Filters By Soot During Fire Events in Nuclear Fuel Cycle Facilities
Takashi Ishibashi, Susumu Tsuchino, Shiro Matsumoto, and Fumio Kasahara
Nuclear Technology | Volume 187 | Number 1 | July 2014 | Pages 57-68
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-94
Efficient Digital Implementation of Signal Processing Algorithms in State-Of-The-Art Field-Programmable Gate Arrays for Gamma-Ray Spectroscopy
Fateme Fahiman, Mahdi Kafaee, Ali Moussavi-Zarandi, and Meisam Fahiman
Nuclear Technology | Volume 187 | Number 1 | July 2014 | Pages 69-81
Technical Paper | Radiation Transport and Protection | doi.org/10.13182/NT13-65
Deployment Strategies for Wireless Sensor Networks in Nuclear Power Plants
Ataul Bariand, Jin Jiang
Nuclear Technology | Volume 187 | Number 1 | July 2014 | Pages 82-95
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT13-1
Computer-Based Investigative Techniques: A Comparison of Dose Using the MCNP Code for Optically Stimulated Light Dosimeters
Thomas B. Rezentes, Mark A. Prelas, Eric Lukosi, Matthew L. Watermann, Jack Crawford, and Richard H. Olsher
Nuclear Technology | Volume 187 | Number 1 | July 2014 | Pages 96-102
Technical Note | Radiation Transport and Protection | doi.org/10.13182/NT11-105
Impact of Local Burnup on Prediction of Power Density in the NIST Research Reactor
Nicholas R. Brown, Albert L. Hanson, and David J. Diamond
Nuclear Technology | Volume 187 | Number 1 | July 2014 | Pages 103-116
Technical Note | Fuel Cycle and Management | doi.org/10.13182/NT13-20
Two-Phase Flow Modeling With Tough2-Mp of A Deep Geological Repository Within the First Benchmark of the FORGE Project
Manuel Lorenzo Sentís
Nuclear Technology | Volume 187 | Number 2 | August 2014 | Pages 117-130
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-84
Extension and Tuning of TOUGH2-MP EOS7R for the Assessment of Deep Geological Repositories for Nuclear Waste: Hydrogen, Arbitrarily Long Decay Chains, and Solubility Limits
Th. U. Kaempfer, Y. Mishin, J. Brommundt, J. Roger, E. Treille, and N. Hubschwerlen
Nuclear Technology | Volume 187 | Number 2 | August 2014 | Pages 131-146
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-80
Modeling Two-Phase-Flow Interactions Across a Bentonite Clay and Fractured Rock Interface
Benoît Dessirier, Jerker Jarsjö, Andrew Frampton
Nuclear Technology | Volume 187 | Number 2 | August 2014 | Pages 147-157
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT13-77
The Effect of Stress on Flow and Transport in Fractured Rock Masses Using an Extended Multiple Interacting Continua Method with Crack Tensor Theory
Zhen Wang, Jonny Rutqvist, Yuan Wang, Colin Leung, Andrew Hoch, Ying Dai
Nuclear Technology | Volume 187 | Number 2 | August 2014 | Pages 158-168
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT13-76
Modeling Transport of Water, Ions, and Chemical Reactions in Compacted Bentonite: Comparison Among Toughreact, Numerrin, and Comsol Multiphysics
Aku Itälä, Mika Laitinen, Merja Tanhua-Tyrkkö, Markus Olin
Nuclear Technology | Volume 187 | Number 2 | August 2014 | Pages 169-174
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT13-79
T2GGM: A Coupled Gas Generation Model for Deep Geologic Disposal of Radioactive Waste
John Avis, Paul Suckling, Nicola Calder, Robert Walsh, Paul Humphreys, Fraser King
Nuclear Technology | Volume 187 | Number 2 | August 2014 | Pages 175-187
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT13-83
Optimizing the Modeling Performance for Safety Assessments of Nuclear Waste Repositories By Approximating Two-Phase Flow and Transport by Single-Phase Transport Simulations
Philipp Schaedle, Nicolas Hubschwerlen, Holger Class
Nuclear Technology | Volume 187 | Number 2 | August 2014 | Pages 188-197
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-82
Design Study on a Fast Reactor Metal Fuel Attaining Very High Burnup
Hirokazu Ohta, Takanari Ogata, Toru Obara
Nuclear Technology | Volume 187 | Number 2 | August 2014 | Pages 198-207
Regular Technical Paper | Fission Reactors | doi.org/10.13182/NT13-105
New Numerical Algorithm Method Considering the Self-Absorption of the Spherical Radioactive Sources Matrix to Calibrate a System of Two Nai Gamma Detectors
Mohamed E. Krar, Ahmed M. El-Khatib, Mohamed S. Badawi
Nuclear Technology | Volume 187 | Number 2 | August 2014 | Pages 208-219
Regular Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT13-109
Analysis of the Limiting Safety System Settings of a Fluoride Salt–Cooled High-Temperature Test Reactor
Yao Xiao, Lin-Wen Hu, Charles Forsberg, Suizheng Qiu, Guanghui Su, Kun Chen, Naxiu Wang
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 221-234
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-93
Modeling the Detection of Delayed Neutron Signatures in MCNP6 and Comparisons with Measurements of 233U, 235U, and 239Pu
M. T. Andrews, J. T. Goorley, E. C. Corcoran, D. G. Kelly
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 235-242
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-72
Application of an Improved Mechanical Shim Control Strategy for AP1000 Reactor
Pengfei Wang, Jiashuang Wan, Shoujun Yan, Yang Liu, Fuyu Zhao
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 243-259
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-111
Preliminary Economic Evaluation of Thorium-Based Fuels in PWRs
M. H. Du Toit, A. C. Cilliers
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 260-269
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-134
An Examination of CANDU Fuel Performance Margins Derived from a Statistical Assessment of Industrial Manufacturing Data
Travis A. Cunning, Paul Chan, Mahesh D. Pandey, Aniket Pant
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 270-281
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-126
Experimental Investigation of a Scaled Water-Cooled Reactor Cavity Cooling System
Rodolfo Vaghetto, Yassin A. Hassan
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 282-293
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-130
Thermal Modeling of High-Level Nuclear Waste Disposal in a Salt Repository
Dylan R. Harp, Philip H. Stauffer, Phoolendra K. Mishra, Daniel G. Levitt, Bruce A. Robinson
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 294-307
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-110
In-Core Flux Sensor Evaluations at the ATR Critical Facility
Troy Unruh, Benjamin Chase, Joy Rempe, David Nigg, George Imel, Jason Harris, Todd Sherman, Jean-François Villard
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 308-315
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT13-122
Cesium Isotope Composition in Fukushima Daiichi Units After Boiling Water Reactor Accident
Masato Takahashi, Kenichi Yoshioka
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 316-327
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-114
Probability Correction Approach to Calibrate High-Purity Germanium Cylindrical Detectors Using Parallelepiped Sources
Sherif S. Nafee
Nuclear Technology | Volume 187 | Number 3 | September 2014 | Pages 328-336
Technical Note | Radiation Transport and Protection | doi.org/10.13182/NT13-106
