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This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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August 4–7, 2024
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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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Recycling of Actinides in Light Water Reactors
Sunanta Patrashakorn, Reiner Papp
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 7-12
Technical Paper | Reactor | doi.org/10.13182/NT80-A32550
An Appraisal of Subcooled Boiling and Slip Ratio from Measurements Made in the Lingen Boiling Water Reactor
G. Nash
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 13-20
Technical Paper | Reactor | doi.org/10.13182/NT80-A32551
Unsteady Dispersed Flow Heat Transfer Under Loss-of-Coolant Accident Related Conditions
A. Ghazanfari, E. F. Hicken, A. Ziegler
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 21-26
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32552
Denitration of Aqueous Waste Solutions from the Nuclear Fuel Reprocessing
M. Kelm, B. Oser, S. Drobnik, W. D. Deckwer
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 27-32
Technical Paper | Chemical Processing | doi.org/10.13182/NT80-A32553
In-Pile Diameter Measurement of Light Water Reactor Test Fuel Rods for Assessment of Pellet-Cladding Mechanical Interaction
Masaaki Uchida, Michio Ichikawa
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 33-44
Technical Paper | Fuel | doi.org/10.13182/NT80-A32554
Behavior of Defective Pressurized Water Reactor Fuel Rods During Power Ramp and Power-Cooling-Mismatch Conditions
Douglas W. Croucher
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 45-57
Technical Paper | Fuel | doi.org/10.13182/NT80-A32555
A Comparison of Models for Electric Generation Planning
Jose L. Del Valle, Mujid S. Kazimi, Fred C. Schweppe
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 58-69
Technical Paper | Economic | doi.org/10.13182/NT80-A32556
Measurements and Calculations of the Neutron Emission Spectra from Materials Used in Fusion-Fission Reactors
L. F. Hansen, C. Wong, T. T. Komoto, B. A. Pohl, R. J. Howerton
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 70-77
Technical Paper | Material | doi.org/10.13182/NT80-A32557
Nondestructive Examination of a Defective Silver Braze Using Resonance-Neutron Radiography
J. W. Behrens, R. A. Schrack, C. D. Bowman
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 78-82
Technical Paper | Analysis | doi.org/10.13182/NT80-A32558
The Use of the Reaction 93Nb(n,n')93mNb for Fast Neutron Flux Measurement
Gad Shani
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 83-86
Technical Paper | Technique | doi.org/10.13182/NT80-A32559
Analysis of the BeO-Reflected Uranium-233 Nitrate Solution Subcritical Multiplication Experiments Conducted at Purnima Laboratories
P. K. Job, M. Srinivasan, V. R. Nargundkar
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 87-96
Technical Note | Reactor | doi.org/10.13182/NT80-A32560
Metal-Matrix Radioactive Waste Forms Prepared by Electrochemical/Gravity Co-Deposition
N. H. Macmillan, R. Roy, P. T. B. Shaffer
Nuclear Technology | Volume 51 | Number 1 | November 1980 | Pages 97-99
Technical Note | Radioactive Waste | doi.org/10.13182/NT80-A32561
Characterization of Liquid-Metal Fast Breeder Reactor Engineering Mechanics Effort by Lines-of-Assurance
Stanley H. Fistedis
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 271-289
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32567
A Quasi-Eulerian Fluid-Structure Code for Simulation of High-Pressure Transients in Core Components
James M. Kennedy, Ted B. Belytschko, Daniel F. Schoeberle
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 290-302
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32568
Effects of Cracks on the Response of Circular Cylindrical Shells
Henry J. Petroski, John L. Glazik, Jr.
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 303-316
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32569
The Dynamic Response of Cracked Fast Reactor Subassembly Ducts
John L. Glazik, Jr., Henry J. Petroski
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 317-331
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32570
A Eulerian Method for Analyzing Above-Core Hydrodynamics and Sodium Spillage During a Hypothetical Core Disruptive Accident
Chung-Yi Wang
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 332-348
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32571
Three-Dimensional Nonlinear Structural Model for Above-Core Structures
James M. Kennedy
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 349-362
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32572
Arbitrary Lagrangian-Eulerian Method for Transient Fluid-Structure Interactions
Han Y. Chu
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 363-377
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32573
Theory and Application of Three-Dimensional Treatment of Pool-Type Liquid-Metal Fast Breeder Reactor Components
Ronald F. Kulak
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 378-387
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32574
Validation of Primary Containment Computer Codes
Yao W. Chang, Joseph Gvildys
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 388-399
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32575
Analysis of High-Energy Excursions Using the Implicit Continuous-Fluid Eulerian Containment Code (ICECO)
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 400-413
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32576
Three-Dimensional Analysis of Reactor Decks and Their Supports
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 414-420
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32577
Analysis of Sodium Spillage from Primary Containment Following Slug Impact
Wayne R. Zeuch, Chung-Yi Wang
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 421-432
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32578
Transient Analysis of a Prestressed Concrete Reactor Vessel for Liquid-Metal Fast Breeder Reactor Primary Containment
Algirdas H. Marchertas, Ted B. Belytschko
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 433-442
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32579
Increasing Primary Containment Capabilities of Liquid-Metal Fast Breeder Reactor Plants by the Use of Prestressed Concrete
Ralph W. Seidensticker, Algirdas H. Marchertas, Zdeněk P. Bažant
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 443-451
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32580
Recent Applications and Improvements of the Hydrodynamic-Structural Piping Code ICEPEL
M. T. A-Moneim
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 452-463
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32581
Three-Dimensional Finite Element Formulation for Elastic-Plastic Nonlinear Analysis of Piping Systems
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 464-475
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32582
Events Contributing to Internal Loading of Secondary Containment: An Integrated Approach
Wayne R. Zeuch
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 476-488
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32583
Potential Advantages of Prestressed Concrete for Liquid-Metal Fast Breeder Reactor Secondary Containment
Ralph W. Seidensticker, Howard L. Schreyer
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 489-498
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32584
Perspective: Mechanics Applications to Fast Breeder Reactor Safety
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 499-500
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety | doi.org/10.13182/NT80-A32585
Basic Research for Evaluating Nuclear Waste Form Performance
Don J. Bradley
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 111-122
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste | doi.org/10.13182/NT80-A32589
The Nature of Glass Leaching
G. L. McVay, C. Q. Buckwalter
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 123-129
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste | doi.org/10.13182/NT80-A32590
Self-Diffusion Processes in Oxide Glasses
G. H. Frischat
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 130-135
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste | doi.org/10.13182/NT80-A32591
X-Ray Photoelectron Spectroscopy Studies of Silicate Glasses: Implications to Bonding and Leaching
B. W. Veal, D. J. Lam, A. P. Paulikas, D. P. Karim
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 136-142
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste | doi.org/10.13182/NT80-A32592
Uranium and Thorium Disequilibrium in Zeolitically Altered Rock
John N. Rosholt
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 143-146
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste | doi.org/10.13182/NT80-A32593
Application of Field-Flow Fractionation to Radioactive Waste Disposal
Marcus N. Myers, Kathy A. Graff, J. Calvin Giddings
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 147-155
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste | doi.org/10.13182/NT80-A32594
Diffusion Coefficients and Their Use
J. F. Relyea
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 156-161
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste | doi.org/10.13182/NT80-A32595
Extended X-Ray Absorption Fine Structure Studies of Actinide Ions in Aqueous Solution
Douglas P. Karim, P. Georgopoulos, G. S. Knapp
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 162-168
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste | doi.org/10.13182/NT80-A32596
Oxidation State Specific Detection of Transuranic Ions in Solution
James V. Beitz, Jan P. Hessler
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 169-177
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Fuel Cycle | doi.org/10.13182/NT80-A32597
Possible Applications of the Mössbauer Technique in Waste Management Studies
S. L. Ruby
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 178-181
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste | doi.org/10.13182/NT80-A32598
Rock Alteration and Mineral Transformations for Nuclear Waste Management
Philip A. Helmke
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 182-187
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste | doi.org/10.13182/NT80-A32599
Aspects of Feldspar Dissolution
P. C. Fung, G. W. Bird, N. S. Mcintyre, G. G. Sanipelli, V. J. Lopata
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 188-196
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste | doi.org/10.13182/NT80-A32600
Stability of Glass in the Geologic Environment: Some Evidence from Studies of Natural Silicate Glasses
Robert A. Zielinski
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 197-200
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste | doi.org/10.13182/NT80-A32601
Summary: Workshop Recommendations—Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management
A. M. Friedman, D. J. Lam, M. G. Seitz
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 201-202
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management | doi.org/10.13182/NT80-A32602
Fuel Cycle Utilizing Plutonium-238 as a“Heat Spike” for Proliferation Resistance
W. R. Waltz, W. L. Godfrey, A. K. Williams
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 203-216
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Fuel Cycle | doi.org/10.13182/NT80-A32603
Critical Experiments Supporting Close Proximity Water Storage of Power Reactor Fuel
Gary S. Hoovler, M. Neil Baldwin, Ray L. Eng, Fred G. Welfare
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 217-237
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Fuel | doi.org/10.13182/NT80-A32604
Cascade Performance for Large Separation Factors
George Emanuel*
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 238-243
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Isotopes Separation | doi.org/10.13182/NT80-A32605
A New Neutron Detection Technique: Fissile Resistors
M. Roche, J. Morin, R. Musart, B. Pierre
Nuclear Technology | Volume 51 | Number 2 | December 1980 | Pages 244-258
Technical Paper | Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Technique | doi.org/10.13182/NT80-A32606
