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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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Nuclear Technology
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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A Model of the Dynamic Behavior of the Coaxial-Flow Gaseous-Core Nuclear Reactor
Kyle H. Turner, Jr., Joseph D. Clement
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 5-14
Technical Paper | Reactor | doi.org/10.13182/NT73-A31329
On the Emission Coefficient of Uranium Plasmas
R. T. Schneider, H. D. Campbell, J. M. Mack
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 15-26
Technical Paper | Reactor | doi.org/10.13182/NT73-A31330
Effect of Neutron Irradiation on the Elastic Constants of Type-304 Stainless Steel
J. L. Straalsund, C. K. Day
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 27-34
Technical Paper | Materials | doi.org/10.13182/NT73-2
Radiation Doses from Hypothetical Exposures to Rulison Gas
C. J. Barton, R. E. Moore, S. R. Hanna
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 35-50
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT73-A31332
Effects of Gas Mixture, Electrode Spacing, Gas Pressure, and Applied Voltage on the Gamma Performance of Fission Counters
L. D. Philipp, N. C. Hoitink, W. G. Spear, M. R. Wood
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 51-59
Technical Paper | Instrument | doi.org/10.13182/NT73-A31333
Continuous Conversion of Uranium/Plutonium Nitrates to Oxides
N. Levitz, D. E. Grosvenor, S. Vogler, F. G. Teats, N. Quattropani
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 60-63
Technical Note | Chemical Processing | doi.org/10.13182/NT73-A31334
Proton Dosimeter Design for Distributed Body Organs
G. S. Khandelwal, J. W. Wilson
Nuclear Technology | Volume 20 | Number 1 | October 1973 | Pages 64-67
Technical Note | Instrument | doi.org/10.13182/NT73-A31335
Spectral Analysis of Sampled Nuclear Reactor Plant Data with Heterodyne Digital Filtering Techniques
H. Roggenbauer, W. Seifritz, T. Lindmo
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 79-85
Technical Paper | Reactor | doi.org/10.13182/NT73-A31343
Determination of Optimum Fuel Loadings in Pressurized Water Reactors Using Dynamic Programming
Richard B. Stout, Alan H. Robinson
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 86-102
Technical Paper | Fuel Cycle | doi.org/10.13182/NT73-A31344
UO2 Pellet-Stack Shortening in a Boiling Water Reactor
F. List, P. Knudsen
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 103-108
Technical Paper | Fuel | doi.org/10.13182/NT73-A31345
Use of Metallic Thorium for LWBRs and LWRs
G. B. Zorzoli
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 109-113
Technical Paper | Fuel | doi.org/10.13182/NT73-A31346
First Report on Apparatus to Simulate In-Reactor Transient Heating Conditions in Oxide Fuel Columns
B. J. Wrona, J. T. A. Roberts, E. Johanson, W. D. Tuohig
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 114-123
Technical Paper | Fuel | doi.org/10.13182/NT73-A31347
Californium-252 Assay System for FBR-Type Fuel Pins
H. O. Menlove, R. A. Forster, J. L. Parker, Darryl B. Smith
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 124-133
Technical Paper | Analysis | doi.org/10.13182/NT73-A31348
Effect of Minor Alloy Variations on the Thermal Densification of Austenitic Stainless Steels
J. F. Bates, M. M. Paxton, J. L. Straalsund
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 134-135
Technical Note | Material | doi.org/10.13182/NT73-A31349
Nuclear Power Plant Heat Rejection in an Arid Climate
Frederic C. Scofield, Rocco A. Fazzolare
Nuclear Technology | Volume 20 | Number 3 | December 1973 | Pages 140-148
Technical Paper | Reactor | doi.org/10.13182/NT73-A31353
Methods for Calculating Vapor and Fuel Transport to the Secondary Containment in an LMFBR Accident
M. F. Kennedy, A. B. Reynolds
Nuclear Technology | Volume 20 | Number 3 | December 1973 | Pages 149-160
Technical Paper | Reactor | doi.org/10.13182/NT73-A31354
A Review of Fusion-Fission (Hybrid) Concepts
B. R. Leonard, Jr.,
Nuclear Technology | Volume 20 | Number 3 | December 1973 | Pages 161-178
Technical Paper | Reactors | doi.org/10.13182/NT73-1
Storage Capacity for Fissile Material as a Function of Facility Size
C. L. Schuske, S. J. Altschuler
Nuclear Technology | Volume 20 | Number 3 | December 1973 | Pages 179-189
Technical Paper | Chemical Processing | doi.org/10.13182/NT73-A31356
Oxygen Interactions Between Sodium and Uranium-Plutonium Oxide Fuel
D. L. Smith
Nuclear Technology | Volume 20 | Number 3 | December 1973 | Pages 190-199
Technical Paper | Fuel | doi.org/10.13182/NT73-A31357
A High-Capacity Annular Centrifugal Contactor
G. J. Bernstein, D. E. Grosvenor, J. F. Lenc, N. M. Levitz
Nuclear Technology | Volume 20 | Number 3 | December 1973 | Pages 200-202
Technical Note | Chemical Processing | doi.org/10.13182/NT73-A31358
