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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Dec 2024
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Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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Evaluation of Effective Prompt Neutron Lifetime for Pressurized Water Reactors
Heba K. Louis
Nuclear Technology | Volume 188 | Number 1 | October 2014 | Pages 1-7
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-120
Feasibility Study of a Soluble Boron–Free Small Modular Integral Pressurized Water Reactor
Justin Mart, Andrew Klein, Alexey Soldatov
Nuclear Technology | Volume 188 | Number 1 | October 2014 | Pages 8-19
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-135
A DFM/Fuzzy/ATHEANA Human Failure Analysis of a Digital Control System for a Pressurizer
J. M. O. Pinto, P. F. Frutuoso E Melo, P. L. C. Saldanha
Nuclear Technology | Volume 188 | Number 1 | October 2014 | Pages 20-33
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-48
Moderator Displacers for Reducing Coolant Void Reactivity in CANDU Reactors: A Scoping Study
Robert Farkas, Eleodor Nichita
Nuclear Technology | Volume 188 | Number 1 | October 2014 | Pages 34-44
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-128
Modeling and Analysis of a Heat Transport Transient Test Facility for Space Nuclear Systems
Adam R. Wheeler, Andrew C. Klein
Nuclear Technology | Volume 188 | Number 1 | October 2014 | Pages 45-62
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-100
Combining Insights from Probabilistic and Deterministic Safety Analyses in Option 4 from the IAEA Specific Safety Guide SSG-2
Milorad Dusic, Mark Dutton, Horst Glaeser, Joachim Herb, Javier Hortal, Rafael Mendizábal, Fernando Pelayo
Nuclear Technology | Volume 188 | Number 1 | October 2014 | Pages 63-77
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-16
A Three-Dimensional Computational Analysis of One-Way Fluid-Structure Coupling in Main Steam Isolation Valve
Li Wu, Jian Xiao, Hong Chen, Jia Li, Songzhi Jiang, Tongmin Wang
Nuclear Technology | Volume 188 | Number 1 | October 2014 | Pages 78-82
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT13-127
Measurement of Molten Chloride Salt Flow and Demonstration of Simulated Fission Product Removal Using a Zeolite Column Apparatus for Spent Salt Treatment in Pyroprocessing
Koichi Uozumi, Takatoshi Hijikata, Takeshi Tsukada, Tadafumi Koyama, Takayuki Terai, Akihiro Suzuki
Nuclear Technology | Volume 188 | Number 1 | October 2014 | Pages 83-96
Technical Paper | Reprocessing | doi.org/10.13182/NT13-49
Simulations for Developing a Flag-Based Active Neutron Interrogation Method for Explosives Detection in Sea-Land Cargo Containers
Adrienne L. Lehnert, Kimberlee J. Kearfott
Nuclear Technology | Volume 188 | Number 1 | October 2014 | Pages 97-111
Technical Paper | Radiation Measurements and General Instrumentation | doi.org/10.13182/NT11-125
Conceptual Design Enhancement for Prevention and Mitigation of Severe Accidents
Jin Ho Song
Nuclear Technology | Volume 188 | Number 2 | November 2014 | Pages 113-122
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-125
Impact of Accident-Tolerant Fuels and Claddings on the Overall Fuel Cycle: A Preliminary Systems Analysis
Gilles J. Youinou, R. Sonat Sen
Nuclear Technology | Volume 188 | Number 2 | November 2014 | Pages 123-138
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT14-22
Evaluation of Helical-Cruciform Fuel Rod Assemblies for High-Power-Density LWRs
T. M. Conboy, T. J. McKrell, M. S. Kazimi
Nuclear Technology | Volume 188 | Number 2 | November 2014 | Pages 139-153
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-104
Approach for Validating Actinide and Fission Product Compositions for Burnup Credit Criticality Safety Analyses
Georgeta Radulescu, Ian C. Gauld, Germina Ilas, John C. Wagner
Nuclear Technology | Volume 188 | Number 2 | November 2014 | Pages 154-171
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-154
Pyroelectric Energy Scavenging Techniques for Self-Powered Nuclear Reactor Wireless Sensor Networks
Scott R. Hunter, Nickolay V. Lavrik, Panos G. Datskos, Dwight Clayton
Nuclear Technology | Volume 188 | Number 2 | November 2014 | Pages 172-184
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT13-136
Study on an Optimal Condition of Closed Chamber Distillation Equipment for Regeneration of LiCl-KCl Eutectic Salt Containing Rare Earth Phosphates
Hee-Chul Eun, Jung Hoon Choi, Yung Zun Cho, In Hak Cho, Hwan Seo Park, Geun Il Park
Nuclear Technology | Volume 188 | Number 2 | November 2014 | Pages 185-191
Technical Paper | Reprocessing | doi.org/10.13182/NT13-146
Corrosion of 316L Stainless Steel Alloy and Hastelloy-N Superalloy in Molten Eutectic LiF-NaF-KF Salt and Interaction with Graphite
Robert S. Sellers, Wei-Jen Cheng, Brian C. Kelleher, Mark H. Anderson, Kumar Sridharan, Chaur-Jeng Wang, Todd R. Allen
Nuclear Technology | Volume 188 | Number 2 | November 2014 | Pages 192-199
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT13-95
Extraction of Uranium from Seawater: Design and Testing of a Symbiotic System
Mathieu Picard, Camille Baelden, You Wu, Le Chang, Alexander H. Slocum
Nuclear Technology | Volume 188 | Number 2 | November 2014 | Pages 200-217
Technical Paper | Miscellaneous | doi.org/10.13182/NT13-144
Verification and Validation of the ENDF/B-VII.1–Based Continuous-Energy Data Tables for MCNP6
Jeremy Lloyd Conlin, D. Kent Parsons, Steven J. Gardiner, Mark Gray, A. C. Kahler, M. Beth Lee, Morgan C. White
Nuclear Technology | Volume 188 | Number 2 | November 2014 | Pages 218-227
Technical Note | Fission Reactors | doi.org/10.13182/NT13-153
Experimental Demonstration of a Heat Pipe–Stirling Engine Nuclear Reactor
David I. Poston, Patrick R. McClure, David D. Dixon, Marc A. Gibson, Lee S. Mason
Nuclear Technology | Volume 188 | Number 3 | December 2014 | Pages 229-237
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-71
Neutronics Studies of Uranium-Bearing Fully Ceramic Microencapsulated Fuel for Pressurized Water Reactors
Nathan Michael George, Ivan Maldonado, Kurt Terrani, Andrew Godfrey, Jess Gehin, Jeff Powers
Nuclear Technology | Volume 188 | Number 3 | December 2014 | Pages 238-251
Technical Paper | Fission Reactors | doi.org/10.13182/NT14-3
Evaluation of Accumulated Fission Products in the Contaminated Water at the Fukushima Daiichi Nuclear Power Plant
Shunsuke Uchida, Masanori Naitoh, Hiroaki Suzuki, Hidetoshi Okada, Satoshi Konishi
Nuclear Technology | Volume 188 | Number 3 | December 2014 | Pages 252-265
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-152
An Approach for Validating Actinide and Fission Product Burnup Credit Criticality Safety Analyses: Criticality (keff) Predictions
J. M. Scaglione, D. E. Mueller, J. C. Wagner
Nuclear Technology | Volume 188 | Number 3 | December 2014 | Pages 266-279
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT13-151
Plug Design for Deep Borehole Disposal of High-Level Nuclear Waste
E. A. Bates, A. Salazar, M. J. Driscoll, E. Baglietto, J. Buongiorno
Nuclear Technology | Volume 188 | Number 3 | December 2014 | Pages 280-291
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT12-166
Development of Natural Circulation Analytical Model in Super-COPD Code and Evaluation of Core Cooling Capability in Monju During a Station Blackout
Fumiaki Yamada, Yoshitaka Fukano, Hiroshi Nishi, Mamoru Konomura
Nuclear Technology | Volume 188 | Number 3 | December 2014 | Pages 292-321
Technical Note | Fission Reactors | doi.org/10.13182/NT13-56
Optimized Flux Trap Dimensions in a Research Reactor Core
P. Savva, S. Chatzidakis, M. Varvayanni, A. Ikonomopoulos, N. Chrysanthopoulou, N. Catsaros, M. Antonopoulos-Domis
Nuclear Technology | Volume 188 | Number 3 | December 2014 | Pages 322-335
Technical Note | Fission Reactors | doi.org/10.13182/NT13-108
