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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Apr 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Latest Red Book stresses need for boosts in uranium development
The latest edition of Uranium 2024: Resources, Production and Demand, commonly known as the Red Book, reports that current uranium resources are sufficient to meet low- and high-growth nuclear capacity needs through 2050 and beyond, but that further development of resources is still required. Even if nuclear capacity remains stable at 2050 levels through the end of the century, the report noted that cumulative demand “could exceed the current identified uranium resource base of nearly 8 million tonnes by the 2080s under the low-growth demand scenario and by the 2110s under the high-growth demand scenario outlined in this edition.”
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Passive System Reliability Analysis: A Study on the Isolation Condenser
Luciano Burgazzi
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 3-9
Technical Paper | doi.org/10.13182/NT139-3-9
Severe Accident Related Research and Development at Forschungszentrum Karlsruhe for Present and Future Needs
Werner Scholtyssek, Gerhard Heusener, Fritz Hofmann, Helmut Plitz
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 10-20
Technical Paper | doi.org/10.13182/NT02-A3298
The Model of the IBR-2 Pulsed Reactor Dynamics and Investigation of Pulse Energy Stabilization
Alexander K. Popov, Juri N. Pepyolyshev, Eugene A. Bondarchenko
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 21-29
Technical Paper | doi.org/10.13182/NT02-A3299
Regulatory Concerns on the In-Containment Water Storage System of the Korean Next Generation Reactor
Hyung-Joon Ahn, Jae-Hun Lee, Young-Seok Bang, Hho-Jung Kim
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 30-35
Technical Note | doi.org/10.13182/NT02-A3300
General Safety Criteria for the Korean Next Generation Reactor
Jae-Hun Lee, Woong-Sik Kim, Young Gill Yune, Jae-Seong Lee
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 36-41
Technical Note | doi.org/10.13182/NT02-A3301
Korean Standard Nuclear Power Plant Response to Common Mode Failure of the Digital Plant Protection System
Cheol Shin Lee, Chan Eok Park, Chul Jin Choi, Jong Tae Seo
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 42-49
Technical Note | doi.org/10.13182/NT02-A3302
Definition and Analysis of an Experimental Benchmark on Shutdown Rod Worths in LEU-HTR Configurations
Rakesh Chawla, Om Parkash Joneja, Marc Rosselet, Tony Williams
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 50-60
Technical Paper | Reactor Safety | doi.org/10.13182/NT02-A3303
A Methodology for Selecting High Thermal-Hydraulic Performance Fuel Configurations for Tightly Packed Epithermal Core Designs
Antonino Romano, Neil E. Todreas
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 61-71
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3304
Empirical and Computational Pressure Drop Correlations for Pressurized Water Reactor Fuel Spacer Grids
Wang Kee In, Dong Seok Oh, Tae Hyun Chun
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 72-79
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3305
Criticality Analysis of MOX and LEU Assemblies for Transport and Storage at the Balakovo Nuclear Power Plant
Sedat Goluoglu, R. T. Primm III
Nuclear Technology | Volume 139 | Number 1 | July 2002 | Pages 80-88
Technical Note | Criticality of Nuclear Materials | doi.org/10.13182/NT02-A3306
Investigation of the Effect of Fixed Absorbers on the Reactivity of PWR Spent Nuclear Fuel for Burnup Credit
John C. Wagner, Charlotta E. Sanders
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 91-126
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3307
Fuel-Coolant Interactions: Visualization and Mixing Measurements
Eric P. Loewen, Riccardo Bonazza, Michael L. Corradini, Robert E. Johannesen
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 127-144
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3308
Transport Characteristics of Selected Pressurized Water Reactor LOCA-Generated Debris
Arup K. Maji, Daseri V. Rao, Bruce Letellier, Luke Bartlein, Brooke Marshall
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 145-155
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3309
Building Up an On-Line Plant Information System for the Emergency Response Center of the Hungarian Nuclear Safety Directorate
János Végh, Csaba Major, Csaba Horváth, Zoltán Hózer, Ferenc Adorján, Iván Lux, Kristóf Horváth
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 156-166
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT02-A3310
Test of Actinide-Lanthanide Separation in an Aluminum-Based Pyrochemical System
Laurence Rault, Murielle Heusch, Michel Allibert, Florent Lemort, Xavier Deschanel, Roger Boen
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 167-174
Technical Paper | Reprocessing | doi.org/10.13182/NT02-A3311
Startup of the Fission Converter Epithermal Neutron Irradiation Facility at the MIT Reactor
Thomas H. Newton, Jr., Kent J. Riley, Peter J. Binns, Gordon E. Kohse, Lin-Wen Hu, Otto K. Harling
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 175-183
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT02-A3312
Simulation and Analysis of Experimental Blowdown and Small-Break Loss-of-Coolant Scenarios with RETRAN-3D
Rafael Macian, Paul Coddington
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 185-204
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3313
Visualization and Measurement of Subcooled Water Jet Injection into High-Temperature Melt by Using High-Frame-Rate Neutron Radiography
Yasuteru Sibamoto, Yutaka Kukita, Hideo Nakamura
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 205-220
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3314
Adequacy of the Heat-Mass Transfer Analogy to Simulate Containment Atmospheric Cooling in the New Generation of Advanced Nuclear Reactors: Experimental Confirmation
Luis E. Herranz, Antonio Campo
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 221-232
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3315
Development and Assessment of the Appendix K Version of RELAP5-3D for LOCA Licensing Analysis
Thomas K. S. Liang, Chin-Jang Chang, Huan-Jen Hung
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 233-252
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3316
Development of the Diamex Process for Treating PHWR High-Level Liquid Waste
L. B. Kumbhare, D. R. Prabhu, G. R. Mahajan, S. Sriram, V. K. Manchanda, L. P. Badheka
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 253-262
Technical Paper | Reprocessing | doi.org/10.13182/NT02-A3317
A Real-Time Graphic Simulator to Monitor Spent Nuclear Fuel Dismantlement Devices
Soon-Hyuk Hong, Jae Wook Jeon, Tai Gil Song, Jong Youl Lee, Sung Hyun Kim, Ji Sup Yoon
Nuclear Technology | Volume 139 | Number 3 | September 2002 | Pages 263-273
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3318
