ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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
Latest Journal Issues
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.
Jump to:
Computational Fluid Dynamics and Thermal-Hydraulic Analyses of SLIMM Reactor Passive Decay Heat Removal by Natural Circulation of Ambient Air
Luis Palomino, Mohamed S. El-Genk
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 1-14
Technical Paper | doi.org/10.13182/NT15-102
Two-Dimensional Axisymmetric Thermostructural Analysis of APR1400 Reactor Vessel Lower Head for Full-Core Meltdown Accident
Hyo-Nam Kim, Ihn Namgung
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 15-28
Technical Paper | doi.org/10.13182/NT15-17
A Scaling Analysis for a Filtered Containment Venting System
Jin Ho Song, Hyun-Joung Jo, Kwang Soon Ha, Jaehoon Jung, Sang Mo An, Hwan Yeol Kim, S. T. Revankar
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 29-43
Technical Paper | doi.org/10.13182/NT15-128
Evaluation of Pulsed Sphere Time-of-Flight and Neutron Attenuation Experimental Benchmarks Using MCNP6’s Unstructured Mesh Capabilities
Joel A. Kulesza, Roger L. Martz
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 44-54
Technical Paper | doi.org/10.13182/NT15-121
Evaluation of the Kobayashi Analytical Benchmark Using MCNP6’s Unstructured Mesh Capabilities
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 55-70
Technical Paper | doi.org/10.13182/NT15-122
Research on an Alarm Method for Initial Loose Parts in a Nuclear Reactor Based on Fractal Theory
Li-Xian Fang, Sheng-Yan Lin, Fu Zeng, Chi-Hu Wang, Yong-Cheng Xie
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 71-78
Technical Paper | doi.org/10.13182/NT15-62
Measurement of Boron Concentration with the Serpentuator System
Jun Li, Xiao-Bin Tang, Long-Gang Gui, Yun Ge, Ying Chen, Da Chen
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 79-86
Technical Paper | doi.org/10.13182/NT15-72
Total Hemispherical Emissivity of Grade 91 Ferritic Alloy with Various Surface Conditions
Christopher B. Azmeh, Kyle L. Walton, Tushar K. Ghosh, Sudarshan K. Loyalka, Dabir S. Viswanath, Robert V. Tompson
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 87-97
Technical Paper | doi.org/10.13182/NT15-54
Fuel Assembly Oscillation-Induced Flow in Initially Stagnant Fluid
Noah A. Weichselbaum, Shadman Hussain, Morteza Rahimi-Abkenar, Majid T. Manzari, Philippe M. Bardet
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 98-104
Technical Note | doi.org/10.13182/NT15-93
Investigation of the Dual-Cooled Annular Fuel Effect on the Thermal Power Uprate in a VVER-1000 Nuclear Reactor
G. R. Ansarifar, M. H. Esteki, M. Zaidabadi
Nuclear Technology | Volume 195 | Number 1 | July 2016 | Pages 105-109
Technical Note | doi.org/10.13182/NT15-90
Metrics for the Technical Performance Evaluation of Light Water Reactor Accident-Tolerant Fuel
Shannon M. Bragg-Sitton, Michael Todosow, Robert Montgomery, Christopher R. Stanek, Rose Montgomery, W. Jon Carmack
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 111-123
Technical Paper | doi.org/10.13182/NT15-149
Estimation of Inherent Safety Margins in Loaded Commercial Spent Nuclear Fuel Casks
Kaushik Banerjee, Kevin R. Robb, Georgeta Radulescu, John M. Scaglione, John C. Wagner, Justin B. Clarity, Robert A. LeFebvre, Joshua L. Peterson
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 124-142
Technical Paper | doi.org/10.13182/NT15-112
Operations Optimization of Nuclear Hybrid Energy Systems
Jun Chen, Humberto E. Garcia, Jong Suk Kim, Shannon M. Bragg-Sitton
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 143-156
Technical Paper | doi.org/10.13182/NT15-130
CFD Analysis and Design of Detailed Target Configurations for an Accelerator-Driven Subcritical System
Adam Kraus, Elia Merzari, Tanju Sofu, Zhaopeng Zhong, Yousry Gohar
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 157-168
Technical Paper | doi.org/10.13182/NT15-99
Comparison of Wireless Sensor Network Routing Protocols Under Gamma Radiation for Nuclear and Space Applications
Michael Nishimura, Yu Liu, Liqian Li, Karen Colins
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 169-180
Technical Paper | doi.org/10.13182/NT15-159
Thermochemical Compatibility and Oxidation Resistance of Advanced LWR Fuel Cladding
T. M. Besmann, Y. Yamamoto, K. A. Unocic
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 181-191
Technical Paper | doi.org/10.13182/NT15-132
Iodine Atom Diffusion in SiC and Zirconium with First-Principles Calculations
Ruixuan Han, Liucheng Liu, Rui Tu, Wei Xiao, Yingying Li, Huailin Li, Dan Shao
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 192-203
Technical Paper | doi.org/10.13182/NT15-109
Corrosion of INCONEL Alloy 625 in Molten LiCl-Li2O-Li
Augustus Merwin, Dev Chidambaram
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 204-212
Technical Paper | doi.org/10.13182/NT15-126
Development of a Low-Temperature Irradiation Capsule for Research Reactor Materials at HANARO
Kee Nam Choo, Man Soon Cho, Sung Woo Yang, Byung Hyuk Jun, Myong Seop Kim
Nuclear Technology | Volume 195 | Number 2 | August 2016 | Pages 213-221
Technical Note | doi.org/10.13182/NT15-154
Design Summary of the Mark-I Pebble-Bed, Fluoride Salt–Cooled, High-Temperature Reactor Commercial Power Plant
Charalampos Andreades, Anselmo T. Cisneros, Jae Keun Choi, Alexandre Y. K. Chong, Massimiliano Fratoni, Sea Hong, Lakshana R. Huddar, Kathryn D. Huff, James Kendrick, David L. Krumwiede, Michael R. Laufer, Madicken Munk, Raluca O. Scarlat, Nicolas Zweibaum, Ehud Greenspan, Xin Wang, Per Peterson
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 223-238
Technical Paper | doi.org/10.13182/NT16-2
Observed Redox Potential Range of Li2BeF4 Using a Dynamic Reference Electrode
Brian Kelleher, Kieran Dolan, Mark Anderson, Kumar Sridharan
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 239-252
Technical Paper | doi.org/10.13182/NT15-140
Exchange Current Density and Diffusion Layer Thickness in Molten LiCl-KCl Eutectic: A Modeling Perspective for Pyroprocessing of Metal Fuels
Suddhasattwa Ghosh, Krishan Kumar, Aligati Venkatesh, P. Venkatesh, Bandi Prabhakara Reddy
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 253-272
Technical Paper | doi.org/10.13182/NT16-37
Nonjudgmental Dynamic Fuel Cycle Benchmarking
Anthony Michael Scopatz
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 273-287
Technical Paper | doi.org/10.13182/NT15-153
Challenging Fuel Cycle Modeling Assumptions: Facility and Time-Step Discretization Effects
Robert W. Carlsen, Paul P. H. Wilson
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 288-300
Technical Paper | doi.org/10.13182/NT15-138
Verification of Safety in Safety Critical Computer-Based Systems: A Case Study of Nuclear Power Plant System
Lalit Singh, Hitesh Rajput
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 301-309
Technical Paper | doi.org/10.13182/NT15-151
Fueling Study of a CANDU Reactor Using Fuels Containing Burnable Neutron Absorbers
Jason J. Song, Paul K. Chan, Hugues W. Bonin, Stéphane Paquette
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 310-328
Technical Paper | doi.org/10.13182/NT16-1
The Hydrogen Issue in the Initial Operation of a Filtered Containment Venting System
Young Su Na, Song-Won Cho, Kwang Soon Ha
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 329-334
Technical Paper | doi.org/10.13182/NT15-160
A Nuclear Renewable Oil Shale System for Economic Dispatchable Low-Carbon Electricity and Liquid Fuels
D. J. Curtis, C. W. Forsberg
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 335-352
Technical Paper | doi.org/10.13182/NT16-14
Using the Sound of Nuclear Energy
Steven Garrett, James Smith, Robert Smith, Brenden Heidrich, Michael Heibel
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 353-362
Technical Paper | doi.org/10.13182/NT16-8
The Gamma Atmospheric Dispersion Factor for Finite-Cloud Radiation Dose Computations
John N. Hamawi
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 363-370
Technical Note | doi.org/10.13182/NT16-18
