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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
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
Jan 2023
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Nuclear Science and Engineering
February 2023
Nuclear Technology
Fusion Science and Technology
January 2023
Latest News
A fateful day for nuclear waste policy: January 31, 1998
Next week will mark 25 years since January 31, 1998, a familiar date to most in the nuclear community, and revisited in today’s #ThrowbackThursday post with an article from the March 1998 issue of Nuclear News. “Those in the nuclear power industry are aware of the significance of the date January 31, 1998. ln the Nuclear Waste Policy Act of 1982, that date was set as the deadline for the U.S. government—more specifically, the Department of Energy—to begin taking possession of and responsibility for spent nuclear fuel from nuclear power plants nationwide” (NN, March 1998, p. 59).
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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT13-52
