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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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Void Swelling in Metals and Alloys Under Irradiation: An Assessment of the Theory
L. K. Mansur
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 5-34
Technical Paper | Critical Review | doi.org/10.13182/NT78-2
Calculation of the Scale Factor for Inference of Pressurized Water Reactor Core Barrel Motion from Neutron Noise Spectral Density
J. C. Robinson, F. Shahrokhi, R. C. Kryter
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 35-46
Technical Paper | Reactor | doi.org/10.13182/NT78-A26697
Quantification of Core Barrel Motion Using an Analytically Derived Scale Factor and Statistical Reactor Noise Descriptors
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 47-51
Technical Paper | Reactor | doi.org/10.13182/NT78-A26698
Potential Radiological Consequences of a Multiple Steam Generator Tube Rupture
Roy R. Fray
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 52-61
Technical Paper | Reactor | doi.org/10.13182/NT78-A26699
Fuel and Fission Gas Response to Simulated Thermal Transients: Experimental Results and Correlation with Fission Gas Release and Swelling Model
G. Bandyopadhyay
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 62-78
Technical Paper | Fuel | doi.org/10.13182/NT78-A26700
Application of the Warm Water Injection Method to Improve the Efficiency of In-Core Wet Sipping for Leaker Detection
Shunsuke Uchida, Motoaki Utamura, Hideo Yusa, Hideo Maki
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 79-88
Technical Paper | Fuel | doi.org/10.13182/NT78-A26701
Oxygen Getters for Fast Reactor Fuel Pins
C. E. Johnson, D. C. Fee
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 89-97
Technical Paper | Material | doi.org/10.13182/NT78-A26702
How Does One Predict and Measure Radiation Damage?
F. A. Nichols
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 98-105
Technical Paper | Material | doi.org/10.13182/NT78-A26703
Effects of Recent Modeling Developments in Prompt Burst Hypothetical Core Disruptive Accident Calculations
J. J. Sienicki, P. B. Abramson
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 106-115
Technical Note | Reactor | doi.org/10.13182/NT78-A26704
Rationale for Incorporating Inservice Inspection Requirements During Nuclear Power Plant Design/Fabrication
Gary J. Dau
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 122-128
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Education | doi.org/10.13182/NT78-A26708
Materials and Design Interaction in Advanced Reactors
J. Boulton
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 129-137
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Education | doi.org/10.13182/NT78-A26709
The Effect of Swelling and Creep on Liquid-Metal Fast Breeder Reactor Performance
W. P. Barthold, J. C. Beitel
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 138-148
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Material | doi.org/10.13182/NT78-A26710
On the Probability of Loss of dc Power Following ac Failure in a Nuclear Power Plant
J. Chun, G. E. Apostolakis
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 149-158
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Reactor | doi.org/10.13182/NT78-A26711
Operation of the Water-to-Sodium Leak Detection System at the Experimental Breeder Reactor II
Marilyn M. Osterhout
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 159-169
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Reactor | doi.org/10.13182/NT78-A26712
Calculation of Radiological Dose due to Release of Tritium Oxides from Controlled Thermonuclear Reactors
T. E. McKone, W. E. Kastenberg
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 170-184
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Reactor Siting | doi.org/10.13182/NT78-A26713
The Interactions of Hydrazine, Ferrous Sulfamate, Sodium Nitrite, and Nitric Acid in Nuclear Fuel Processing Solutions
Leonard W. Gray
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 185-193
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Chemical Processing | doi.org/10.13182/NT78-A26714
Neutron Irradiation Effects on Carbon and Graphite Cloths and Fibers
W. J. Gray
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 194-207
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Material | doi.org/10.13182/NT78-A26715
Injecting Irradiation Samples with a Uniform Concentration of Helium Using Curium-244
N. H. Packan, W. A. Coghlan
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 208-213
Technical Paper | Tutorial Materials/Design Interaction in Nuclear System / Radiation | doi.org/10.13182/NT78-A26716
High-Level Radioactive Waste Incorporation into (Special) Cements
Della M. Roy, George R. Gouda
Nuclear Technology | Volume 40 | Number 2 | September 1978 | Pages 214-219
Technical Note | Tutorial Materials/Design Interaction in Nuclear System / Chemical Processing | doi.org/10.13182/NT78-A26717
Heat Cost in a Swedish Agrothermal Plant
Jörgen Christensen
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 227-233
Technical Paper | Reactor | doi.org/10.13182/NT78-A26720
Energy Cascading in Large District Heating Systems
Franz Wolfgang Mayer
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 234-239
Technical Paper | Reactor | doi.org/10.13182/NT78-A26721
Ice Pond Cooling of a Power Plant
George C. Geisler, J. A. Urbanski, W. F. Witzig
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 240-247
Technical Paper | Reactor | doi.org/10.13182/NT78-A26722
Sensitivity of Peak Cladding Temperatures to Loss-of-Coolant Accident Reflood Parameters
Richard N. Oehlberg, Harold H. Scott
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 248-260
Technical Paper | Reactor | doi.org/10.13182/NT78-A26723
The Effects of Nozzle-to-Target Distance on Wastage in Small-Leak Sodium-Water Reactions
Naomichi Kanegae, Koh Hashiguchi, Ichiro Ikemoto, Masao Hori
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 261-277
Technical Paper | Reactor | doi.org/10.13182/NT78-A26724
Investigation of Activity Release During Light Water Reactor Core Meltdown
H. Albrecht, V. Matschoss, H. Wild
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 278-283
Technical Paper | Reactor Siting | doi.org/10.13182/NT78-A26725
Subcriticality Guidelines for Liquid-Metal Fast Breeder Reactor Spent Fuel Shipping Cask Designs
J. S. Philbin, S. A.Dupree
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 284-296
Technical Paper | Fuel Cycle | doi.org/10.13182/NT78-A26726
Chemical Thermodynamics of the System Cs-U-Zr-H-I-O in the Light Water Reactor Fuel-Cladding Gap
Theodore M. Besmann, Terrence B. Lindemer
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 297-305
Technical Paper | Fuel | doi.org/10.13182/NT78-A26727
An Improved Finite Difference Method to Evaluate Heat Transfer in Fuel Pins with Eccentrically Placed Pellets
G. W. McNair, K. L. Peddicord
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 306-314
Technical Paper | Fuel | doi.org/10.13182/NT78-A26728
Migration of Radionuclide Chains in Groundwater
V. C. Rogers
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 315-320
Technical Paper | Radioactive Waste | doi.org/10.13182/NT78-A26729
A Criticism on Fuel Rod Structural Analysis
K. Lassmann
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 321-328
Technical Paper | Material | doi.org/10.13182/NT78-A26730
Influence of Flow-Field Structure on Uranium Isotope Separation in the Separation Nozzle
W. Berkhahn, W. Ehrfeld, G. Krieg
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 329-340
Technical Paper | Isotope Separation | doi.org/10.13182/NT78-A26731
Temperature Measurement by Ratio Pyrometers of Melting Pool Surfaces
A. Mack
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 341-347
Technical Paper | Technique | doi.org/10.13182/NT78-A26732
The Sensitivity of the First Wall Radiation Damage to Fusion Reactor Blanket Composition
J. M. Barnes, R. T. Santoro, T. A. Gabriel
Nuclear Technology | Volume 40 | Number 3 | October 1978 | Pages 348-451
Technical Note | Material | doi.org/10.13182/NT78-A26733
