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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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:
The Near Boiling Reactor: Design of a Small, Inherently Safe, Nuclear Reactor to Extend the Operational Envelope of the Victoria-Class Submarine
Christopher Cole, Hugues Bonin
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 1-14
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3852
Assessment of Regenerative Reheating in Direct Brayton Power Cycles for High-Temperature Gas-Cooled Reactors
Luis E. Herranz, José I. Linares, Beatriz Y. Moratilla
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 15-24
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3853
Probabilistic Risk Management Using Risk-Based Safety Goals for the Design of Spacecraft with Onboard Nuclear Reactor Systems
Michael V. Frank, William E. Kastenberg
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 25-38
Technical Paper | Reactor Safety | doi.org/10.13182/NT07-A3854
Experiments on a Water Pool-Type Reactor Cavity Cooling System in a High-Temperature Gas-Cooled Reactor
Hyoung Kyu Cho, Yun Je Cho, Moon Oh Kim, Goon Cherl Park
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 39-58
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3855
Adsorption of Uranium on a Novel Bioadsorbent-Chitosan-Coated Perlite
Shameem Hasan, Tushar K. Ghosh, Mark A. Prelas, Dabir S. Viswanath, Veera M. Boddu
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 59-71
Technical Paper | Reprocessing | doi.org/10.13182/NT07-A3856
Advances in the Subcritical, Gas-Cooled, Fast Transmutation Reactor Concept
W. M. Stacey, K. A. Boakye, S. K. Brashear, A. C. Bryson, K. A. Burns, E. J. Bruch, S. A. Chandler, O. M. Chen, S. S. Chiu, J.-P. Floyd, C. J. Fong, S. P. Hamilton, P. B. Johnson, S. M. Jones, M. Kato, B. A. MacLaren, R. P. Manger, B. L. Meriwether, C. Mitra, K. R. Riggs, B. H. Shrader, J. C. Schulz, C. M. Sommer, T. S. Sumner, J. S. Wagner, J. B. Weathers, C. P. Wells, F. H. Willis, Z. W. Friis, J. I. Marquez-Danian, R. W. Johnson, C. de Oliveira, H. K. Park, D. W. Tedder
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 72-105
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT07-A3857
The Design, Construction, and Preliminary Experiment of China's ADS Subcritical Experimental Assembly Venus-1
Yong-Qian Shi, Pu Xia, Zhang-Lin Luo, Zhi-Xiang Zhao, Dazhao Ding, Yi-Guo Li, Qin-Fu Zhu, Hai-Hong Xia, Ji-Gen Li, Wei Zhang, Jian Cao, Yan-Hui Quan, Huang-Da Luo, Xiaofei Wu
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 106-118
Technical Paper | Accelerators | doi.org/10.13182/NT07-A3858
Lithium-6-Based Passive Reactivity Control Devices for a Gas-Cooled Fast Reactor
W. F. G. van Rooijen, J. L. Kloosterman, T. H. J. J. van der Hagen, H. van Dam
Nuclear Technology | Volume 159 | Number 2 | August 2007 | Pages 119-133
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3859
Characteristics and Behavior of High-Burnup Fuel That May Affect the Source Terms for Cask Accidents
Robert E. Einziger, Carl Beyer
Nuclear Technology | Volume 159 | Number 2 | August 2007 | Pages 134-146
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3860
Optimization of the Hybrid Sulfur Cycle for Nuclear Hydrogen Generation
Yong Hoon Jeong, Mujid S. Kazimi
Nuclear Technology | Volume 159 | Number 2 | August 2007 | Pages 147-157
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3861
A Three-Dimensional CFD Model for a Performance Verification of the Liquid Poison Injection System of a CANDU-6 Reactor
Bo Wook Rhee, Hangbok Choi, Joo Hwan Park, Kyung Myung Chae, Hye Jeong Yun
Nuclear Technology | Volume 159 | Number 2 | August 2007 | Pages 158-166
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3862
Methodologies for the Probabilistic Risk Assessment of Digital Reactor Protection and Control Systems
Tunc Aldemir, Don W. Miller, Michael Stovsky, Jason Kirschenbaum, Paolo Bucci, L. Anthony Mangan, Audeen Fentiman, Steven A. Arndt
Nuclear Technology | Volume 159 | Number 2 | August 2007 | Pages 167-191
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT07-A3863
Fire Durations of Concern for a Modern Legal-Weight Truck Cask
Neelima Mallidi, Miles Greiner, Venkata V. R. Venigalla
Nuclear Technology | Volume 159 | Number 2 | August 2007 | Pages 192-201
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT07-A3864
Real-Time Measurement of Material Elastic Properties in a High Gamma Irradiation Environment
R. S. Schley, K. L. Telschow, J. B. Walter, D. L. Cottle
Nuclear Technology | Volume 159 | Number 2 | August 2007 | Pages 202-207
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT07-A3865
Monte Carlo Modeling of Count Rates and Defects in a Silicon Carbide Detector Neutron Monitor System, Highlighting GT-MHR
Behrooz Khorsandi, Mehdi Reisi Fard, Thomas E. Blue, Don W. Miller, Wolfgang Windl
Nuclear Technology | Volume 159 | Number 2 | August 2007 | Pages 208-220
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT07-A3866
Highly Sensitive Laser Diode Detection of CsCl
Edward Augustyniak, Aleksander Ershov, Jacek Borysow
Nuclear Technology | Volume 159 | Number 2 | August 2007 | Pages 221-226
Technical Note | Radiation Measurements and Instrumentation | doi.org/10.13182/NT07-A3867
Introduction to the Beryllium Technology Special Issue
Glen R. Longhurst
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Page 227
Technical Paper | Beryllium Technology | doi.org/10.13182/NT07-A3868
Effect of Ti Content on Compatibility Between Be-Ti and SS316LN
K. Tsuchiya, H. Kawamura, T. Ishida
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 228-232
Technical Paper | Beryllium Technology | doi.org/10.13182/NT07-A3869
Structural and Oxidation Studies of Titanium Beryllides
E. Alves, L. C. Alves, N. Franco, M. R. Da Silva, A. Paúl
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 233-237
Technical Paper | Beryllium Technology | doi.org/10.13182/NT07-A3870
Beryllium Layer Deposition on Carbon and Tungsten from Beryllium-Seeded Plasmas
K. Schmid, M. J. Baldwin, R. P. Doerner, D. Nishijima
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 238-244
Technical Paper | Beryllium Technology | doi.org/10.13182/NT07-A3871
Magnetic Field Effects on Tritium Release from Neutron-Irradiated Beryllium Pebbles
Juris Tiliks, Gunta Kizane, Aigars Vitins, Elina Kolodinska, Elisa Rabaglino
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 245-249
Technical Paper | Beryllium Technology | doi.org/10.13182/NT07-A3872
Use of a Paraffin-Based Grout to Stabilize Buried Beryllium and Other Wastes
Gretchen E. Matthern, Neal A. Yancey, Darrel L. Knudson, Duane J. Hanson
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 250-255
Technical Paper | Beryllium Technology | doi.org/10.13182/NT07-A3873
Automatic Search of the Power Ascension Path for a Boiling Water Reactor Using Genetic Algorithm and Neural Network
Chi-Szu Lee, Chaung Lin
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 256-266
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3874
A Modular Metal-Fuel Fast Reactor with One-Loop Main Cooling System
Yoshitaka Chikazawa, Yasushi Okano, Mamoru Konomura, Koji Sato, Naoki Sawa, Hiroyuki Sumita, Shigeyuki Nakanishi, Masato Ando
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 267-278
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3875
Liquid-Metal Bond for LWR Fuel Rods
Doonyapong Wongsawaeng, Donald Olander
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 279-291
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3876
Simulation of Two-Phase Flow in Complex Systems
Wolfgang Wulff
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 292-309
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3877
Natural Convection's Transient Behavior
S. Usman, B. S. Mohammad, S. Abdallah
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 310-318
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3878
A Methodology for Experimental and 3-D Computational Radiation Transport Assessments of Pu-Be Neutron Sources
Gabriel Ghita, Glenn Sjoden, James Baciak
Nuclear Technology | Volume 159 | Number 3 | September 2007 | Pages 319-331
Technical Paper | Radiation Protection | doi.org/10.13182/NT07-A3879
