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Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Nuclear Science and Engineering
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Nuclear Technology
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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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Evaluation of the Fluid-Structure Interaction Effects in a Lead-Cooled Fast Reactor
R. Lo Frano
Nuclear Technology | Volume 189 | Number 1 | January 2015 | Pages 1-10
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-23
Modeling and SISO/MIMO Control with an Inverse Nyquist Array and Stability Analysis for Load-Follow Operation of PWR Core Without Boron
Gang Li
Nuclear Technology | Volume 189 | Number 1 | January 2015 | Pages 11-29
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-115
Evaluation of External Event Effects on JSFR Fuel Handling System
Atsushi Katoh, Yoshitaka Chikazawa, Masayuki Uzawa, Fumiaki Kaneko, Akihiro Ide
Nuclear Technology | Volume 189 | Number 1 | January 2015 | Pages 30-44
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-147
Measurements of Charged Aerosol Coagulation
Matthew P. Simones, Sudarshan K. Loyalka
Nuclear Technology | Volume 189 | Number 1 | January 2015 | Pages 45-62
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-14
Implications of Plutonium Isotopic Separation on Closed Fuel Cycles and Repository Design
Charles Forsberg
Nuclear Technology | Volume 189 | Number 1 | January 2015 | Pages 63-70
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-137
Analysis of Loss-of-Flow Accidents for the NIST Research Reactor with Fuel Conversion from HEU to LEU
J. S. Baek, A. Cuadra, L.-Y. Cheng, A. L. Hanson, N. R. Brown, D. J. Diamond
Nuclear Technology | Volume 189 | Number 1 | January 2015 | Pages 71-86
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-124
Fault-Tolerant Architecture and Reliability Analysis for NISS-RPS
Dong Hoon Kim, Gwang Seop Son, Choul Woong Son, Dong Young Lee
Nuclear Technology | Volume 189 | Number 1 | January 2015 | Pages 87-102
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT13-142
On the Solution of the Nonlinear Fractional Neutron Point-Kinetics Equation with Newtonian Temperature Feedback Reactivity
A. Patra, S. Saha Ray
Nuclear Technology | Volume 189 | Number 1 | January 2015 | Pages 103-109
Technical Note | Reactor Safety | doi.org/10.13182/NT13-148
Selector-Valve Failed Fuel Detection and Location System for Japan Sodium-Cooled Fast Reactor
Kosuke Aizawa, Kaoru Fujita, Hideki Kamide, Naoto Kasahara
Nuclear Technology | Volume 189 | Number 2 | February 2015 | Pages 111-121
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-156
The Behavior of Radiolytically Produced Hydrogen in a High-Level Liquid Waste Tank of a Reprocessing Plant: Hydrogen Concentration in the Ventilated Tank Air
Hiroshi Kinuhata, Yoji Shirato, Masahiro Tomiyama, Takashi Kodama, Masanao Nakano, Takeshi Yasuda, Koichi Tsutagi, Yasuyuki Yoshino, Yoshinobu Nakamura, Yoshikazu Tamauchi, Shingo Matsuoka
Nuclear Technology | Volume 189 | Number 2 | February 2015 | Pages 122-132
Technical Paper | Reprocessing | doi.org/10.13182/NT14-11
Experimental Investigation of the Interaction Kinetics Between Metallic Melt and Special Concrete
S. M. An, K. S. Ha, B. T. Min, H. Y. Kim, J. H. Song
Nuclear Technology | Volume 189 | Number 2 | February 2015 | Pages 133-142
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-24
Tagging-Gas Failed Fuel Detection and Location System for Sodium-Cooled Reactors
Kosuke Aizawa, Yoshitaka Chikazawa
Nuclear Technology | Volume 189 | Number 2 | February 2015 | Pages 143-151
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-161
Assessment of the Potential of By-Product Recovery of Thorium to Satisfy Demands of a Future Thorium Fuel Cycle
Timothy Ault, Steven Krahn, Allen Croff
Nuclear Technology | Volume 189 | Number 2 | February 2015 | Pages 152-162
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-19
Effect of Thermal Conductivity Degradation for High-Burnup Fuel During a Postulated Control Element Assembly Ejection Accident
Seok-Hee Ryu, Kil-Sup Um, Jae-Il Lee
Nuclear Technology | Volume 189 | Number 2 | February 2015 | Pages 163-172
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT14-28
Demonstration of Signature-Based Safeguards for Pyroprocessing as Applied to Electrorefining and the Ingot Casting Process
Philip L. Lafreniere, Devin S. Rappleye, Robert O. Hoover, Michael F. Simpson, Edward D. Blandford
Nuclear Technology | Volume 189 | Number 2 | February 2015 | Pages 173-185
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-35
Parametric Study of Trade-Offs in the Hybrid Transport Theory MAVRIC Methodology for Shielding and Dosimetry Analyses
Benjamin C. Bowers, Bojan Petrovic
Nuclear Technology | Volume 189 | Number 2 | February 2015 | Pages 186-201
Technical Note | Radiation Transport and Protection | doi.org/10.13182/NT12-162
Reactor Physics Scoping and Characterization Study on Implementation of TRIGA Fuel in the Advanced Test Reactor
Jennifer A. Lyons, Wade R. Marcum, Sean Morrell, Mark DeHart
Nuclear Technology | Volume 189 | Number 2 | February 2015 | Pages 202-217
Technical Note | Fission Reactors | doi.org/10.13182/NT14-33
Representing Nuclear Criticality Excursion Experiment Data by an Artificial Neural Network
Peter L. Angelo
Nuclear Technology | Volume 189 | Number 3 | March 2015 | Pages 219-240
Technical Paper | Criticality Safety | doi.org/10.13182/NT14-44
Generation of Graphite Particles by Sliding Abrasion and Their Characterization
Raymond S. Troy, Robert V. Tompson, Tushar K. Ghosh, Sudarshan K. Loyalka, Nidia C. Gallego
Nuclear Technology | Volume 189 | Number 3 | March 2015 | Pages 241-257
Technical Paper | Reactor Safety | doi.org/10.13182/NT14-25
Influence of Carbon Nanotube Dispersion in UO2–Carbon Nanotube Ceramic Matrix Composites Utilizing Spark Plasma Sintering
Andrew Cartas, Haitang Wang, Ghatu Subhash, Ronald Baney, James Tulenko
Nuclear Technology | Volume 189 | Number 3 | March 2015 | Pages 258-267
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-7
Turbine Bypass, Mass Inventory, and Mixed-Mode Generator Power Control of S-CO2 Recompression Cycle
Alexander Heifetz, Richard Vilim
Nuclear Technology | Volume 189 | Number 3 | March 2015 | Pages 268-277
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-113
Conceptual Design of Passive Containment Cooling System for APR-1400 Using Multipod Heat Pipe
Gyeongho Nam, Junseok Park, Sangnyung Kim
Nuclear Technology | Volume 189 | Number 3 | March 2015 | Pages 278-293
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-121
Influence of Solution Chemistry on the Selective Adsorption of Uranium and Thorium Onto Activated Carbon
S. M. Yakout
Nuclear Technology | Volume 189 | Number 3 | March 2015 | Pages 294-300
Technical Paper | Reprocessing | doi.org/10.13182/NT14-39
Microfluidic-Based Sample Chips for Radioactive Solutions
J. L. Tripp, J. D. Law, T. E. Smith, V. J. Rutledge, W. F. Bauer, R. D. Ball, P. A. Hahn
Nuclear Technology | Volume 189 | Number 3 | March 2015 | Pages 301-311
Technical Paper | Radioisotopes | doi.org/10.13182/NT14-5
Radial Density Distribution in Irradiated FBR MOX Fuel Pellets
Akihiro Ishimi, Kozo Katsuyama, Hirofumi Nakamura, Takeo Asaga, Hirotaka Furuya
Nuclear Technology | Volume 189 | Number 3 | March 2015 | Pages 312-317
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT14-34
