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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Nuclear Technology
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Latest News
NextGen MURR Working Group established in Missouri
The University of Missouri’s Board of Curators has created the NextGen MURR Working Group to serve as a strategic advisory body for the development of the NextGen MURR (University of Missouri Research Reactor).
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Relative Proliferation Risks for Different Fuel Cycle Arrangements
Meng Yue, Lap-Yan Cheng, Robert A. Bari
Nuclear Technology | Volume 165 | Number 1 | January 2009 | Pages 1-17
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT09-A4058
Development and Validation of a Porous-Medium Computational Fluid Dynamics Model for a Fast Boron Shutdown System
Timothy J. Drzewiecki, Brian L. Mount, Martin Lopez de Bertodano
Nuclear Technology | Volume 165 | Number 1 | January 2009 | Pages 18-31
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A4059
Validation of the TASS/SMR and MARS Codes for a Natural-Circulation Experiment at the VISTA Facility
Y. J. Chung, S. H. Yang, H. K. Kim, M. K. Chung, K. K. Kim
Nuclear Technology | Volume 165 | Number 1 | January 2009 | Pages 32-42
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A4060
Experimental and Numerical Analysis of Natural Convection in Geometrically Modeled Core Catcher of the Liquid-Metal-Cooled Fast Reactor
Anil Kumar Sharma, Sanjay Kumar Das, J. Harvey
Nuclear Technology | Volume 165 | Number 1 | January 2009 | Pages 43-52
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A4061
A Benchmark System for Comparing Reliability Modeling Approaches for Digital Instrumentation and Control Systems
Jason Kirschenbaum, Paolo Bucci, Michael Stovsky, Diego Mandelli, Tunc Aldemir, Michael Yau, Sergio Guarro, Eylem Ekici, Steven A. Arndt
Nuclear Technology | Volume 165 | Number 1 | January 2009 | Pages 53-95
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT09-A4062
Low-Burnup Irradiation Behavior of Fast Reactor Metal Fuels Containing Minor Actinides
Hirokazu Ohta, Takanari Ogata, Takeshi Yokoo, Michel Ougier, Jean-Paul Glatz, Bruno Fontaine, Laurent Breton
Nuclear Technology | Volume 165 | Number 1 | January 2009 | Pages 96-110
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT09-A4063
Accelerator-Based Target Design and Optimization Driven by High-Energy Electron Beams and Proton Beams for the Analysis of Neutron Generation Characteristics
Yaxi Liu, Man-Sung Yim, David McNelis
Nuclear Technology | Volume 165 | Number 1 | January 2009 | Pages 111-123
Technical Paper | Accelerators | doi.org/10.13182/NT09-A4064
Elemental Analysis of Neutron-Induced Gamma-Ray Spectra for Detection of Hazardous Materials
Bin Liu, Xuefeng Lv, Shiliang Zhou, Ying Wu
Nuclear Technology | Volume 165 | Number 1 | January 2009 | Pages 124-131
Technical Note | Radiation Measurements and Instrumentation | doi.org/10.13182/NT09-A4065
On an Improved Design of a Fluidized Bed Nuclear Reactor - II: Linear Stability and Transient Analysis
Alexander Agung, Danny Lathouwers, Tim H. J. J. van der Hagen, Hugo van Dam, Christopher C. Pain
Nuclear Technology | Volume 165 | Number 2 | February 2009 | Pages 133-144
Technical Paper | Fission Reactors | doi.org/10.13182/NT09-A4081
Transient Heat Transfer Characteristics Between Molten Fuel and Steel with Steel Boiling in the CABRI-TPA2 Test
Hidemasa Yamano, Yu-Ichi Onoda, Yoshiharu Tobita, Ikken Sato
Nuclear Technology | Volume 165 | Number 2 | February 2009 | Pages 145-165
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A4082
Current Status of Knowledge of the Fluoride Salt (FLiNaK) Heat Transfer
J. Ambrosek, M. Anderson, K. Sridharan, T. Allen
Nuclear Technology | Volume 165 | Number 2 | February 2009 | Pages 166-173
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT165-166
Modeling and Simulation of a CANDU Reactor for Control System Design and Analysis
Hooman Javidnia, Jin Jiang, Majid Borairi
Nuclear Technology | Volume 165 | Number 2 | February 2009 | Pages 174-189
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT09-A4084
Actinide Recovery Experiments with Bench-Scale Liquid Cadmium Cathode in Real Fission Product-Laden Molten Salt
Shelly X. Li, S. D. Herrmann, K. M. Goff, M. F. Simpson, R. W. Benedict
Nuclear Technology | Volume 165 | Number 2 | February 2009 | Pages 190-199
Technical Paper | Reprocessing | doi.org/10.13182/NT09-A4085
Preparing High-Loaded Potassium Cobalt Hexacyanoferrate/Silica Composite for Radioactive Wastewater Treatment
Hai-Di Liu, Fu-Zhi Li, Xuan Zhao, Gui-Chun Yun
Nuclear Technology | Volume 165 | Number 2 | February 2009 | Pages 200-208
Technical Paper | Decontamination/decommissioning | doi.org/10.13182/NT09-A4086
Evaluation of Transportation and Acceptance Strategies Associated with the Potential Yucca Mountain Waste Management System
Leah Spradley, Mark Abkowitz, James H. Clarke
Nuclear Technology | Volume 165 | Number 2 | February 2009 | Pages 209-222
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT09-A4087
Actinide Migration in Fractures of Granite Host Rock: Laboratory and In Situ Investigations
Bernhard Kienzler, Peter Vejmelka, Jürgen Römer, Dieter Schild, Mats Jansson
Nuclear Technology | Volume 165 | Number 2 | February 2009 | Pages 223-240
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT09-A4088
Effect of the Intermediate Cooling Process on the Behavior of the Zircaloy-4 Cladding After a High-Temperature Oxidation
Jun Hwan Kim, Byoung Kwon Choi, Yong Hwan Jeong, Seung Jin Oh
Nuclear Technology | Volume 165 | Number 2 | February 2009 | Pages 241-248
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT09-A4089
Measurement and Application of Paralysis Factor for Improved Detector Dead-Time Characterization
Amol Patil, Shoaib Usman
Nuclear Technology | Volume 165 | Number 2 | February 2009 | Pages 249-256
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT09-A4090
Studies on Chemical Speciation of Sodium Aerosols Produced in Sodium Fire
V. Subramanian, P. Sahoo, N. Malathi, R. Ananthanarayanan, R. Baskaran, B. Saha
Nuclear Technology | Volume 165 | Number 3 | March 2009 | Pages 257-269
Technical Paper | Fission Reactors | doi.org/10.13182/NT09-A4100
Technology Gap Analysis on Sodium-Cooled Reactor Fuel-Handling System Supporting Advanced Burner Reactor Development
Yoshitaka Chikazawa, Mitchell Farmer, Christopher Grandy
Nuclear Technology | Volume 165 | Number 3 | March 2009 | Pages 270-292
Technical Paper | Fission Reactors | doi.org/10.13182/NT09-A4101
The ASTEC Integral Code for Severe Accident Simulation
J. P. van Dorsselaere, C. Seropian, P. Chatelard, F. Jacq, J. Fleurot, P. Giordano, N. Reinke, B. Schwinges, H. J. Allelein, W. Luther
Nuclear Technology | Volume 165 | Number 3 | March 2009 | Pages 293-307
Technical Paper | Reactor Safety | doi.org/10.13182/NT09-A4102
Toward an Atomistically Informed Fuel Performance Code: Thermal Properties Using FRAPCON and Molecular Dynamics Simulation
Daniel A. Vega, Taku Watanabe, Susan B. Sinnott, Simon R. Phillpot, James S. Tulenko
Nuclear Technology | Volume 165 | Number 3 | March 2009 | Pages 308-312
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT09-A4103
Numerical Simulation of Free-Surface Vortices
Elia Merzari, Hisashi Ninokata, Sheng Wang, Emilio Baglietto
Nuclear Technology | Volume 165 | Number 3 | March 2009 | Pages 313-320
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A4104
Thermal Analysis of a Fuel-Handling System for Sodium-Cooled Reactor with Minor Actinide-Bearing Metal Fuel
Yoshitaka Chikazawa, Christopher Grandy
Nuclear Technology | Volume 165 | Number 3 | March 2009 | Pages 321-332
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A4105
Integrated Methodology for Thermal-Hydraulic Code Uncertainty Analysis with Application
Mohammad Pourgol-Mohamad, Mohammad Modarres, Ali Mosleh
Nuclear Technology | Volume 165 | Number 3 | March 2009 | Pages 333-359
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT165-333
Removing Acetic Acid from a UREX+ Waste Stream: A Review of Technologies
Jessica A. Mitchell, R. M. Counce, J. S. Watson, B. B. Spencer, G. D. Del Cul
Nuclear Technology | Volume 165 | Number 3 | March 2009 | Pages 360-369
Technical Paper | Reprocessing | doi.org/10.13182/NT09-A4107
Assessment of a High-Throughput Electrorefining Concept for a Spent Metallic Nuclear Fuel - II: Electrohydrodynamic Analysis and Validation
J. H. Lee, K. H. Oh, Y. H. Kang, S. C. Hwang, H. S. Lee, J. B. Shim, E. H. Kim, S. W. Park
Nuclear Technology | Volume 165 | Number 3 | March 2009 | Pages 370-379
Technical Paper | Reprocessing | doi.org/10.13182/NT09-A4108
