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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.
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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
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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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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 Mathematical Model for an Integral Economizer U-Tube Steam Generator
D. C. Arwood, T. W. Kerlin
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 12-32
Technical Paper | Reactor | doi.org/10.13182/NT77-A31847
Thermal Shock Effects in Fast Burst Reactors
G. P. Mulholland, T. F. Luera, A. De La Paz
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 33-39
Technical Paper | Reactor | doi.org/10.13182/NT77-A31848
Isotopic Enrichment of Plasma Exhausts from Controlled Thermonuclear Reactors by Cryogenic Distillation
Balabhadra Misra, Victor A. Maroni
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 40-50
Technical Paper | Reactor | doi.org/10.13182/NT77-A31849
Nuclear Analysis of a Tokamak Experimental Power Reactor Conceptual Design
Mohamed A. Abdou, Jungchung Jung
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 51-79
Technical Paper | Reactor | doi.org/10.13182/NT77-A31850
Migration of Metallic Fission Products in Reactor Oxide Fuels
F. D’Annucci, C. Sari, G. Schumacher
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 80-86
Technical Paper | Reactor | doi.org/10.13182/NT77-A31851
The Importance of Heat Transfer in Hypothetical Core Disruptive Accident Analysis
Paul B. Abramson
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 87-96
Technical Paper | Reactor Siting | doi.org/10.13182/NT77-A31852
Basis for Subcritical Limits in Proposed Criticality Safety Standard for Mixed Oxides
E. D. Clayton, H. K. Clark, D. W. Magnuson,+ J. H. Chalmers,† Gordon Walker,‡ N. Ketzlach, Ryohei Kiyose,++ C. L. Brown, D. R. Smith,††, R. Artigas ‡‡
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 97-111
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31853
Neutron Multiplication and Shielding Problems in Pressurized Water Reactor Spent Fuel Shipping Casks
C. Devillers, P. Blum
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 112-118
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31854
Probability Distributions of Peak-Clad Temperature and Cladding Oxidation Thickness in Loss-of-Coolant Accidents for a Typical Boiling Water Reactor
T. Shimooke, K. Matsumoto
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 119-130
Technical Paper | Fuel | doi.org/10.13182/NT77-A31855
On the Pellet-Cladding Interaction Phenomenon
J. T. A. Roberts, E. Smith, N. Fuhrman, D. Cubicciotti
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 131-144
Technical Paper | Fuel | doi.org/10.13182/NT77-A31856
Simulation Study of the Restructuring of Advanced Fuel Heated in a Radial Temperature Gradient
C. Sari
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 145-153
Technical Paper | Fuel | doi.org/10.13182/NT77-A31857
Study of Uranium-Plutonium Carbide-Based Fuel Simulating High Burnup
U. Benedict, G. Giacchetti, Hj. Matzke, K. Richter, C. Sari, H. E. Schmidt
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 154-161
Technical Paper | Fuel | doi.org/10.13182/NT77-A31858
Simulation of the Nuclear Power Economy
Mark B. Triplett
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 162-172
Technical Paper | Economic | doi.org/10.13182/NT77-A31859
Basic Compatibility Studies of Advanced Fuels with 3d Transition Metals
E. C. Beahm, C. A. Culpepper
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 173-177
Technical Paper | Material | doi.org/10.13182/NT77-A31860
Methods of Shield Analysis for Protection Against Electrons in Space
John W. Wilson, Fred M. Denn
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 178-183
Technical Paper | Shielding | doi.org/10.13182/NT77-A31861
On the Effective Temperature of an Expanding Tube with a Radial Temperature Gradient over the Wall
W. Van Witzenburg, L. G. J. Janssen, J. Prij
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 184-187
Technical Note | Reactor | doi.org/10.13182/NT77-A31862
Processing and Composition Control of Weak-Acid-Resin-Derived Fuel Microspheres
G. W. Weber, R. L. Beatty, V. J. Tennery
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 217-226
Fabrication | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31881
Improved Gas Distributor for Coating High-Temperature Gas-Cooled Reactor Fuel Particles
W. J. Lackey, D. P. Stinton, J. D. Sease
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 227-237
Fabrication | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31882
Coated Fuel Particles: Requirements and Status of Fabrication Technology
H. Huschka, P. Vygen
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 238-245
Fabrication | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31883
Nuclear Fuel Coated Particle Development in the Reactor Fuel Element Laboratories of the U.K. Atomic Energy Authority
P. L. Allen, L. H. Ford, J. V. Shennan
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 246-253
Fabrication | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31884
Fundamentals on the Agglomerate Model and Its Relation to the Physical Properties of Pyrocarbon
J. Linke, K. Koizlik, H. Nickel
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 257-262
Pyrocarbon | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31885
Coated Nuclear Fuel Particles: The Coating Process and Its Model
R. L. R. Lefevre, M. S. T. Price
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 263-278
Pyrocarbon | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31886
Automatic Size Analysis of Coated Fuel Particles
K. Wallisch, P. Koss
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 279-283
Pyrocarbon | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31887
Quality Control Techniques for Pyrocarbon
W. Delle, K. Koizlik, M. S. T. Price U.K., E. Wallura
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 284-292
Pyrocarbon | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31888
A Quantitative Chemical Method for the Determination of the Disordered Carbon Component in Pyrocarbon Coatings of Fuel Particles
E. A. Wolfrum, H. Nickel
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 293-300
Pyrocarbon | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31889
Transmission Electron Microscopy of Pyrocarbon Coatings
E. Pollmann, J. Pelissier, C. S. Yust, J. L. Kaae
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 301-309
Pyrocarbon | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31890
Influence of Porosity on the Irradiation Performance of Pyrocarbon Coatings
P. Krautwasser, H. Nickel
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 310-319
Pyrocarbon | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31891
Properties of Silicon Carbide for Nuclear Fuel Particle Coatings
R. J. Price
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 320-336
Pyrocarbon | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31892
Preliminary Examination of the Helium Permeability of Pyrocarbon Coatings
C. S. Morgan, G. L. Powell
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 337-339
Pyrocarbon | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31893
Properties Influencing High-Temperature Gas-Cooled Reactor Coated Fuel Particle Performance
D. P. Harmon, C. B. Scott
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 343-352
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31894
Neutron-Induced Permeability of Pyrocarbon-Coated High-Temperature Gas-Cooled Reactor Fuel Particles
R. A. Bradley, B. A. Thiele
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 353-358
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31895
The Mechanical Behavior of Biso-Coated Fuel Particles During Irradiation. Part I: Analysis of Stresses and Strains Generated in the Coating of a Biso Fuel Particle During Irradiation
J. L. Kaae
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 359-367
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31896
The Mechanical Behavior of Biso-Coated Fuel Particles During Irradiation. Part II: Prediction of Biso Particle Behavior During Irradiation with a Stress-Analysis Model
J. L. Kaae, R. E. Bullock, C. B. Scott, D. P. Harmon
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 368-378
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31897
Improvement of a Method for Predicting Failure Rates of Coated Particles During Irradiation
Karl Bongartz
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 379-385
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31898
Restoration of Carbon Monoxide Equilibrium in Porous Oxide High-Temperature Reactor Fuel Particles
A. Strigl, E. Proksch
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 386-391
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31899
Amoeba Behavior of UO2 Coated Particle Fuel
M. Wagner-Löffler
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 392-402
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31900
Migration of ThO2 Kernels Under the Influence of a Temperature Gradient
C. L. Smith
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 403-412
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31901
Silicon Carbide Corrosion in High-Temperature Gas-Cooled Reactor Fuel Particles
H. Grübmeier, A. Naoumidis, B. A. Thiele
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 413-427
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31902
Stoichiometric Effects on Performance of High-Temperature Gas-Cooled Reactor Fuels from the U-C-O System
F. J. Homan, T. B. Lindemer, E. L. Long, Jr., T. N. Tiegs, R. L. Beatty
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 428-441
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT35-428
Irradiation Performance of Fort St. Vrain High-Temperature Gas-Cooled Reactor Fuel in Capsule F-30
C. B. Scott, D. P. Harmon
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 442-454
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31904
Cesium Release and Transport in Biso-Coated Fuel Particles
M. T. Morgan, A. P. Malinauskas
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 457-464
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31905
Cesium Release Data for Biso-Coated Particles
D. Stöver, R. Hecker
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 465-474
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31906
Release of Metallic Fission Products from Multilayered Coated Particles
P. D. Smith, R. G. Steinke, D. D. Jensen, T. Hama
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 475-482
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31907
Silver Release from Coated Particle Fuel
H. Nabielek, P. E. Brown, P. Offermann
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 483-493
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT35-483
Emission of Fission Gases by Failed Coated Oxide Fuel Particles
Marie-Louise Pointud, Pierre Chenebault
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 494-500
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31909
Fission Gas Release from Fuel Particles and Fuel Rods
B. F. Myers, N. L. Baldwin, W. E. Bell
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 501-508
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31910
Fission Product Release from Coated Particles Embedded in Spherical Fuel Elements for High-Temperature Reactors
E. Groos, G. Mielken, R. Duwe, A. Müller, M. Will
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 509-515
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31911
Release of Rare Fission Gases from Spherical Elements with Coated Fuel Particles
K. Röllig
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 516-523
Fission Product Release | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31912
Chemical Vapor Deposition of ZrC Made by Reactions of ZrCl4 with CH4 and with C3H6
C. M. Hollabaugh, L. A. Wahman, R. D. Reiswig, R. W. White, P. Wagner
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 527-535
Advanced and Improved Fuel and Application | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31913
Improvements in the Performance of Nuclear Fuel Particles Offered by Silicon-Alloyed Carbon Coatings
J. L. Kaae, S. A. Sterling, L. Yang
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 536-547
Advanced and Improved Fuel and Application | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31914
Metallic Fission Product Retention of Coated Particles with Ceramic Kernel Additives
R. Förthmann, H. Grübmeier, D. Stöver
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 548-556
Advanced and Improved Fuel and Application | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31915
Coated Particle Fuel Element for Pressurized Water Reactors
Werner Katscher
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 557-563
Advanced and Improved Fuel and Application | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31916
A Technical Scale Gas Generator for Steam Gasification of Coal Using Nuclear Heat
H. Jüntgen, K. H. Van Heek
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 581-590
Technical Paper | Reactor | doi.org/10.13182/NT77-A31867
SOPHT—A Computer Model for CANDU-PHWR Heat Transport Networks and Their Control
Charles Yung Fen Chang, John Skears
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 591-602
Technical Paper | Reactor | doi.org/10.13182/NT77-A31868
The Effect of Internal Circulation on the Heat Transfer of a Nuclear Reactor Containment Spray Droplet
J. N. Chung, P. S. Ayyaswamy
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 603-610
Technical Paper | Reactor | doi.org/10.13182/NT77-A31869
Fission and Explosive Energy Releases of PuO2, PuO2-UO2, UO2, and UO3 Assemblies
J. J. Koelling, G. E. Hansen, C. C. Byers
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 611-616
Technical Paper | Reactor Siting | doi.org/10.13182/NT77-A31870
A Generalized Parametric Model for Transient Gas Release and Swelling in Oxide Fuels
E. E. Gruber
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 617-634
Technical Paper | Fuel | doi.org/10.13182/NT77-A31871
Thorium-Based Fuels in Fast Breeder Reactors
Bal Raj Sehgal, Joseph A. Naser, Ching-Lu Lin, Walter B. Loewenstein
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 635-650
Technical Paper | Fuel | doi.org/10.13182/NT77-A31872
Transport of Deuterium in Nb—1 wt% Zr
R. M. Alire
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 651-655
Technical Paper | Material | doi.org/10.13182/NT77-A31873
Interactions of Refractories and Reactor Materials with Sodium
J. K. Fink, J. J. Heiberger, R. Kumar, R. A. Blomquist
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 656-662
Technical Paper | Material | doi.org/10.13182/NT77-A31874
In-Line Determination of Fissile Material in High-Activity Solutions
G. Schulze, H. Würz
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 663-670
Technical Paper | Technique | doi.org/10.13182/NT77-A31875
Elastic-Plastic Analysis of Pressurized Ducts with Rounded Corners
H. J. Petroski
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 671-676
Technical Note | Reactor | doi.org/10.13182/NT77-A31876