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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
2022 ANS Winter Meeting and Technology Expo
November 13–17, 2022
Phoenix, AZ|Arizona Grand 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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Oct 2022
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Nuclear Science and Engineering
October 2022
Nuclear Technology
November 2022
Fusion Science and Technology
Latest News
Former criticality experiment lab demolished at Oak Ridge
Work crews at the Department of Energy’s Oak Ridge Site in Tennessee have successfully completed the demolition of the former Criticality Experiment Laboratory. Crews worked this past summer to bring down the dilapidated 1940s-era facility, also known as Building 9213.
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Analysis of Reactivity Insertion Accidents for the NIST Research Reactor Before and After Fuel Conversion
J. S. Baek, A. Cuadra, L.-Y. Cheng, A. L. Hanson, N. R. Brown, D. J. Diamond
Nuclear Technology | Volume 185 | Number 1 | January 2014 | Pages 1-20
Technical Paper | Fission Reactors | dx.doi.org/10.13182/NT13-26
An Assessment of Corewide Coherency Effects in the Multichannel Modeling of the Initiating Phase of a Severe Accident in a Sodium Fast Reactor
M. Guyot, P. Gubernatis, C. Suteau, R. Le Tellier, J. Lecerf
Nuclear Technology | Volume 185 | Number 1 | January 2014 | Pages 21-38
Technical Paper | Fission Reactors | dx.doi.org/10.13182/NT12-123
Depletion Reactivity Benchmarks—I: Experimental Benchmarks for Quantifying PWR Fuel Reactivity Depletion Uncertainty
K. S. Smith, T. Bahadir, R. Ferrer, D. B. Lancaster, A. J. Machiels
Nuclear Technology | Volume 185 | Number 1 | January 2014 | Pages 39-56
Technical Paper | Fuel Cycle and Management | dx.doi.org/10.13182/NT13-31
Depletion Reactivity Benchmarks—II: Utilization in PWR Spent-Fuel Pool Criticality Analysis
D. B. Lancaster, K. S. Smith, A. J. Machiels
Nuclear Technology | Volume 185 | Number 1 | January 2014 | Pages 57-70
Technical Paper | Fuel Cycle and Management | dx.doi.org/10.13182/NT13-28
Application of Augmented Reality to Nuclear Reactor Core Simulation for Fundamental Nuclear Engineering Education
Kosuke Tsujita, Tomohiro Endo, Akio Yamamoto
Nuclear Technology | Volume 185 | Number 1 | January 2014 | Pages 71-84
Technical Paper | Nuclear Plant Operations and Control | dx.doi.org/10.13182/NT13-7
Installation of a New Neutron Beam Facility at the U.S. Geological Survey TRIGA Reactor
Aaron E. Craft, Jeffrey C. King
Nuclear Technology | Volume 185 | Number 1 | January 2014 | Pages 85-99
Technical Paper | Radiation Measurements and General Instrumentation | dx.doi.org/10.13182/NT13-4
Molten Salt Breeder Reactor Waste Management
Darryl D. Siemer
Nuclear Technology | Volume 185 | Number 1 | January 2014 | Pages 100-108
Technical Note | Reprocessing | dx.doi.org/10.13182/NT12-164
Coupling of a Lumped Parameter and a Finite Difference Model for Estimation of a Reactivity-Induced Transient in a PWR with Annular Fuel Rods
J. P. Duarte, J. J. Rivero, P. F. Frutuoso E Melo, A. C. M. Alvim
Nuclear Technology | Volume 185 | Number 2 | February 2014 | Pages 109-126
Technical Paper | Reactor Safety | dx.doi.org/10.13182/NT12-149
On the Use of Reduced-Moderation LWRs for Transuranic Isotope Burning in Thorium Fuel—I: Assembly Analysis
Benjamin A. Lindley, N. Zara Zainuddin, Paolo Ferroni, Andrew Hall, Fausto Franceschini, Geoffrey T. Parks
Nuclear Technology | Volume 185 | Number 2 | February 2014 | Pages 127-146
Technical Paper | Fuel Cycle and Management | dx.doi.org/10.13182/NT13-53
On the Use of Reduced-Moderation LWRs for Transuranic Isotope Burning in Thorium Fuel—II: Core Analysis
Nuclear Technology | Volume 185 | Number 2 | February 2014 | Pages 147-173
Technical Paper | Fuel Cycle and Management | dx.doi.org/10.13182/NT13-54
Uncertainty Analysis on Reactivity and Discharged Inventory due to 235,238U, 239,240,241Pu, and Fission Products: Application to a Pressurized Water Reactor Fuel Assembly
D. F. Da Cruz, D. Rochman, A. J. Koning
Nuclear Technology | Volume 185 | Number 2 | February 2014 | Pages 174-191
Technical Paper | Fuel Cycle And Management | dx.doi.org/10.13182/NT12-154
Evaluating the Collective Radiation Dose to Workers from the U.S. Once-Through Nuclear Fuel Cycle
Steven L. Krahn, Allen G. Croff, Bethany L. Smith, James H. Clarke, Andrew G. Sowder, Albert J. Machiels
Nuclear Technology | Volume 185 | Number 2 | February 2014 | Pages 192-207
Technical Paper | Fuel Cycle and Management | dx.doi.org/10.13182/NT13-64
A Heat Transfer Approach to the Calculation of Residual Power of Used Nuclear Fuel
Peter Schreiber, Pavol Tanuska, Robert Vrabel, Pavel Vazan
Nuclear Technology | Volume 185 | Number 2 | February 2014 | Pages 208-215
Technical Paper | Thermal Hydraulics | dx.doi.org/10.13182/NT12-138
Microfluidic-Based Robotic Sampling System for Radioactive Solutions
Jack D. Law, Julia L. Tripp, Tara E. Smith, John M. Svoboda, Veronica J. Rutledge, Troy G. Garn, Larry Macaluso
Nuclear Technology | Volume 185 | Number 2 | February 2014 | Pages 216-225
Technical Paper | Reprocessing | dx.doi.org/10.13182/NT13-36
Transient Analysis of Depressurized Loss-of-Forced-Circulation Accident Without Scram in High-Temperature Gas-Cooled Reactor
Hiroyuki Sato, Xing L. Yan, Yukio Tachibana, Kazuhiko Kunitomi, Yukitaka Kato
Nuclear Technology | Volume 185 | Number 3 | March 2014 | Pages 227-238
Technical Paper | Fission Reactors | dx.doi.org/10.13182/NT13-97
Decoupling Control of Canadian Supercritical Water-Cooled Reactors
Peiwei Sun, Jin Jiang, Kai Wang
Nuclear Technology | Volume 185 | Number 3 | March 2014 | Pages 239-258
Technical Paper | Fission Reactors | dx.doi.org/10.13182/NT12-130
A Dual System for Monitoring the Positions of Multiple Radioactive Tracer Pebbles in Scaled Pebble Bed Reactors
Zhijian Wang, Kyoung O. Lee, Robin P. Gardner
Nuclear Technology | Volume 185 | Number 3 | March 2014 | Pages 259-269
Technical Paper | Fission Reactors | dx.doi.org/10.13182/NT13-13
Design Studies of a Low Sodium Void Reactivity Core Able to Accommodate Degraded TRU Fuel
Katsuyuki Kawashima, Kazuteru Sugino, Shigeo Ohki, Tsutomu Okubo
Nuclear Technology | Volume 185 | Number 3 | March 2014 | Pages 270-280
Technical Paper | Fission Reactors | dx.doi.org/10.13182/NT13-38
Meeting the Needs of a Nuclear-Renewables Electrical Grid with a Fluoride-Salt–Cooled High-Temperature Reactor Coupled to a Nuclear Air-Brayton Combined-Cycle Power System
Charles Forsberg, Daniel Curtis
Nuclear Technology | Volume 185 | Number 3 | March 2014 | Pages 281-295
Technical Paper | Fission Reactors | dx.doi.org/10.13182/NT13-58
An Artificial Viscosity for the III-Posed One-Dimensional Incompressible Two-Fluid Model
William D. Fullmer, Sang Yong Lee, Martin A. Lopez De Bertodano
Nuclear Technology | Volume 185 | Number 3 | March 2014 | Pages 296-308
Technical Paper | Thermal Hydraulics | dx.doi.org/10.13182/NT13-66
Size Effect on Nuclear Gamma-Ray Energy Spectra Acquired By Different-Sized CeBr3, LaBr3:Ce, and NaI:Tl Gamma-Ray Detectors
Paul Guss, Michael Reed, Ding Yuan, Denis Beller, Matthew Cutler, Christopher Contreras, Sanjoy Mukhopadhyay, Scott Wilde
Nuclear Technology | Volume 185 | Number 3 | March 2014 | Pages 309-321
Technical Paper | Radiation Transport and Protection | dx.doi.org/10.13182/NT13-2
Comparison of Radionuclide Releases from a Conceptual Geological Repository for RBMK-1500 and BWR Spent Nuclear Fuel
Povilas Poskas, Asta Narkuniene, Dalia Grigaliuniene, Stefan Finsterle
Nuclear Technology | Volume 185 | Number 3 | March 2014 | Pages 322-335
Technical Paper | Radioactive Waste Management and Disposal | dx.doi.org/10.13182/NT13-52
