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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
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!
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Nuclear 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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Improved Reaction Rate Tracking and Fission Product Yield Determinations for the Monte Carlo-Linked Depletion Capability in MCNPX
Michael L. Fensin, John S. Hendricks, Samim Anghaie
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 3-12
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4003
Neptunium in the Fuel Cycle: Nonproliferation Benefits Versus Industrial Drawbacks
Selena Ng, Dominique Grenèche, Bernard Guesdon, Richard Vinoche, Marc Delpech, Florence Dolci, Hervé Golfier, Christine Poinot-Salanon
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 13-19
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4004
Coupled Neutronic and Thermal-Hydraulic Out-of-Phase Stability of Supercritical Water-Cooled Reactors
Jiyun Zhao, Pradip Saha, Mujid S. Kazimi
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 20-33
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4005
Dynamics of Molten Salt Reactors
Jiri Krepel, Ulrich Rohde, Ulrich Grundmann, Frank-Peter Weiss
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 34-44
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4006
Development of Analytical Procedures of Two-Phase Flow in Tight-Lattice Fuel Bundles for Innovative Water Reactor for Flexible Fuel Cycle
Hiroyuki Yoshida, Akira Ohnuki, Takeharu Misawa, Kazuyuki Takase, Hajime Akimoto
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 45-54
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4007
Validation of the CATHARE2 Code Against Oberhausen II Data
Fabrice Bentivoglio, Nicolas Tauveron
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 55-75
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4008
Large Eddy Simulation of Highly Fluctuational Temperature and Velocity Fields Observed in a Mixing-Tee Experiment
Pierre Coste, Patrick Quemere, Pierre Roubin, Philippe Emonot, Masaaki Tanaka, Hideki Kamide
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 76-88
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4009
Heat Transfer for Subcooled Flow Boiling in Hypervapotron Configuration
Peipei Chen, Wen Wu, Barclay G. Jones, Ty A. Newell
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 89-96
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4010
Experimental Results of Pebble Bed Thermal-Hydraulic Characteristics
Sigitas Rimkevicius, Eugenijus Uspuras
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 97-102
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4011
Temperature and Flow Distributions in Sodium-Heated Large Straight Tube Steam Generator by Numerical Methods
Naoyuki Kisohara, Takeshi Moribe, Takaaki Sakai
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 103-118
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4012
Experimental Investigation on the Heat Transfer Characteristics in Upward Flow of Supercritical Carbon Dioxide
Hyungrae Kim, Yoon Yeong Bae, Hwan Yeol Kim, Jin Ho Song, Bong Hyun Cho
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 119-129
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4013
Compatibility of Selected Ni-Based Alloys in Molten Li,Na,Be/F Salts with PuF3 and Tellurium Additions
Victor Ignatiev, Aleksandr Surenkov, Ivan Gnidoi, Vladimir Fedulov, Vadim Uglov, Valery Afonichkin, Andrei Bovet, Vladimir Subbotin, Aleksandr Panov, Andrei Toropov
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 130-142
Technical Paper | Icapp '06 | doi.org/10.13182/NT08-A4014
Assessment of Two-Phase Flow Heat Transfer Correlations for Molten Core-Concrete Interaction Study
B. Tourniaire, O. Varo
Nuclear Technology | Volume 164 | Number 1 | October 2008 | Pages 143-151
Technical Note | Icapp '06 | doi.org/10.13182/NT164-143
Numerical Modeling of the Gas Migration Test at the Grimsel Test Site (Switzerland)
Rainer Senger, Bill Lanyon, Paul Marschall, Stratis Vomvoris, Ai Fujiwara
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 155-168
Technical Paper | Tough206 | doi.org/10.13182/NT08-A4016
Sensitivity Analysis for Joint Inversion of Ground-Penetrating Radar and Thermal-Hydrological Data from a Large-Scale Underground Heater Test
M. B. Kowalsky, J. Birkholzer, J. Peterson, S. Finsterle, S. Mukhopadhyay, Y. Tsang
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 169-179
Technical Paper | Tough206 | doi.org/10.13182/NT08-A4017
Modeling Reactive Multiphase Flow and Transport of Concentrated Solutions
Guoxiang Zhang, Nicolas Spycher, Eric Sonnenthal, Carl Steefel, Tianfu Xu
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 180-195
Technical Paper | Tough206 | doi.org/10.13182/NT08-A4018
Using TOUGHREACT to Model Laboratory Tests on the Interaction of NaNO3-NaOH Fluids with Sandstone Rock at a Deep Radionuclide Repository Site
A. V. Kiryukhin, E. P. Kaymin, E. V. Zakharova
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 196-206
Technical Paper | Tough206 | doi.org/10.13182/NT08-A4019
Lessons Learned from Sodium-Cooled Fast Reactor Operation and Their Ramifications for Future Reactors with Respect to Enhanced Safety and Reliability
J. Guidez, L. Martin, S. C. Chetal, P. Chellapandi, Baldev Raj
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 207-220
Technical Paper | Fission Reactors | doi.org/10.13182/NT08-A4020
An Enhanced Code for the Safety Analysis of Pool-Type Sodium-Cooled Fast Reactors
Kwi Seok Ha, Hae Yong Jeong, Young Min Kwon, Yong Bum Lee, Dohee Hahn, James E. Cahalan, Floyd E. Dunn
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 221-231
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A4021
Experimental Investigations on the ESBWR Stability Performance
C. P. Marcel, M. Rohde, T. H. J. J. Van der Hagen
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 232-244
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A4022
Radiolytic Oxidation of Ruthenium Oxide Deposits
C. Mun, L. Cantrel, C. Madic
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 245-254
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A4023
Spherical Fuel Element Concept for Small Reactor Design
Kenneth Geelhood, Dean Matson, David Senor, Chad Painter
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 255-264
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A4024
RELAP5 Analyses of Thermal-Hydraulic Behavior in Steam Generator U-Tubes During Reflux Condensation
Noritoshi Minami, Toshiaki Chikusa, Michio Murase
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 265-277
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A4025
Experimental Study and Model Development on the Moisture Effect for Nuclear Graphite Oxidation
Eung Soo Kim, Chang Ho Oh, Hee Cheon No
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 278-285
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT08-A4026
Advanced Polymer Composites for the Fabrication of Spent Nuclear Fuel Disposal Containers
Hugues W. Bonin, Ian Miedema, Van Tam Bui
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 286-304
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT08-A4027
Nondestructive Determination of Relative Plutonium Content in MOX Fuel Pins for Pressurized Heavy Water Reactors Using Passive Gamma Scanning
K. V. Vrinda Devi, T. Soreng, J. P. Panakkal, H. S. Kamath
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 305-308
Technical Note | Radiation Measurements and Instrumentation | doi.org/10.13182/NT08-A4028
Technology Assessment of Boiling Water Reactor Steam Supply Acoustic Performance and Wet Steam Sound Speed
Arthur E. Ruggles
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 309-319
Technical Paper | Fission Reactors | doi.org/10.13182/NT08-A4029
Optimized Core Design of a Supercritical Carbon Dioxide-Cooled Fast Reactor
Christopher S. Handwerk, Michael J. Driscoll, Pavel Hejzlar
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 320-336
Technical Paper | Fission Reactors | doi.org/10.13182/NT08-A4030
Conservative Width of High-Burnup Structure in Light Water Reactor UO2 Fuel as a Function of Pellet Average Burnup
Yang-Hyun Koo, Byung-Ho Lee, Jae-Yong Oh, Kun-Woo Song
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 337-347
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT08-A4031
Nuclear Energy for a Low-Carbon-Dioxide-Emission Transportation System with Liquid Fuels
Charles W. Forsberg
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 348-367
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT164-348
Performance Evaluation of the Safety Analysis Codes for Subcooled Boiling in a Nuclear Reactor Downcomer During the Late Reflood Phase of an LBLOCA
D. J. Euh, B. G. Huh, B. J. Yun, C.-H. Song, I. G. Kim
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 368-384
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT164-368
Heat Transfer Issues Associated with a Hypothetical Failure of the MEGAPIE Spallation Source Target Window
Brian L. Smith, Sergey V. Shepel
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 385-409
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A4034
Technology Gap Analysis on Sodium-Heated Steam Generators Supporting Advanced Burner Reactor Development
Yoshitaka Chikazawa, Mitchell Farmer, Christopher Grandy
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 410-432
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT08-A4035
Electrochemical Reduction of MOX Pellets in Molten Lithium Chloride Based on a Practical Operating Condition
Masaki Kurata, Noboru Yahagi, Shinichi Kitawaki, Akira Nakayoshi, Mineo Fukushima
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 433-441
Technical Paper | Reprocessing | doi.org/10.13182/NT08-A4036
Radionuclide Transport in a Water-Saturated Planar Fracture with Bentonite Extrusion
R. A. Borrelli, Joonhong Ahn
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 442-464
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT08-A4037
EBR-II Superheater Duplex Tube Examination
Daniel M. Wachs, Dennis D. Keiser, Douglas L. Porter, Naoyuki Kisohara
Nuclear Technology | Volume 164 | Number 3 | December 2008 | Pages 465-473
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT08-A4038
