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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
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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Comparison of Two- and Three-Dimensional Calculations of Super Prompt Critical Excursions
A. Birkhofer, A. Schmidt, W. Werner
Nuclear Technology | Volume 24 | Number 1 | October 1974 | Pages 7-12
Technical Paper | Reactor | doi.org/10.13182/NT74-A31456
Transient Critical Heat Flux and Spacer Grid Studies
L. A. Zielke, R. H. Wilson
Nuclear Technology | Volume 24 | Number 1 | October 1974 | Pages 13-19
Technical Paper | Reactor | doi.org/10.13182/NT74-A31457
Fission Gas Behavior in Fast Reactor Fuel Under Transient Power Conditions
J. W. Dias, D. Okrent, R. C. Erdmann
Nuclear Technology | Volume 24 | Number 1 | October 1974 | Pages 20-32
Technical Paper | Reactor | doi.org/10.13182/NT74-A31458
An Equilibrium Approach to Optimal in-Core Fuel Management for Pressurized Water Reactors
Krishan Chitkara, Joel Weisman
Nuclear Technology | Volume 24 | Number 1 | October 1974 | Pages 33-49
Technical Paper | Fuel Cycle | doi.org/10.13182/NT74-A31459
Fabrication Procedures for Unalloyed Molybdenum
A. J. Moorhead, J. R. DiStefano, R. E. McDonald
Nuclear Technology | Volume 24 | Number 1 | October 1974 | Pages 50-63
Technical Paper | Material | doi.org/10.13182/NT74-A31460
The Effect of Oxygen on the Corrosion of Vanadium and V-20% Ti by Liquid Lithium
J. H. DeVan, R. L. Klueh
Nuclear Technology | Volume 24 | Number 1 | October 1974 | Pages 64-72
Technical Paper | Material | doi.org/10.13182/NT74-A31461
A General Approach to the Design of Radiation Gauges
A. Notea, Y. Segal
Nuclear Technology | Volume 24 | Number 1 | October 1974 | Pages 73-80
Technical Paper | Instrument | doi.org/10.13182/NT74-A31462
Gamma-Ray Assay of Low-Enriched Uranium Waste
R. B. Walton, E. I. Whitted, R. A. Forster
Nuclear Technology | Volume 24 | Number 1 | October 1974 | Pages 81-92
Technical Paper | Instrument | doi.org/10.13182/NT74-A31463
Empirical Swelling Equations for Solution-Annealed Type 304 Stainless Steel
John P. Foster, Robert V. Strain
Nuclear Technology | Volume 24 | Number 1 | October 1974 | Pages 93-98
Technical Note | Material | doi.org/10.13182/NT74-A31464
Digital Period Meter
W. R. Sheets
Nuclear Technology | Volume 24 | Number 1 | October 1974 | Pages 99-101
Technical Note | Instrument | doi.org/10.13182/NT74-A31465
Sensitivity of Fast Reactor Static and Dynamic Parameters to Different Fission-Product Cross-Section Data
D. Ilberg, D. Saphier, S. Yiftah
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 111-122
Technical Paper | Reactor | doi.org/10.13182/NT74-A31468
Theoretical and Experimental Study of Phenix Steam Generator Prototype Modules
L. Duchatelle, L. de Nucheze, M. G. Robin
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 123-136
Technical Paper | Reactor | doi.org/10.13182/NT74-A31469
Scaling Considerations of Experimental Post-LOCA Steam Relief
J. R. Brodrick, P. A. Lowe, W. E. Burchill
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 137-148
Technical Paper | Reactor | doi.org/10.13182/NT74-A31470
Gas Tag Identification of Failed Fuel—I. Synergistic Use of Inert Gases
N. J. McCormick, R. E. Schenter
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 149-155
Technical Paper | Reactor | doi.org/10.13182/NT74-1
Gas Tag Identification of Failed Fuel — II. Resolution Between Single and Multiple Failures
N. J. McCormick
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 156-167
Technical Paper | Reactor | doi.org/10.13182/NT74-2
ORRIBLE—A Computer Program for Flow and Temperature Distribution in 19-Rod LMFBR Fuel Subassemblies
J. L. Wantland
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 168-175
Technical Paper | Fuel | doi.org/10.13182/NT74-A31473
Temperature Distribution in the Duct Wall and at the Exit of a 19-Rod Simulated LMFBR Fuel Assembly (FFM Bundle 2A)
M. H. Fontana, R. E. MacPherson, P. A. Gnadt, L. F. Parsly, J. L. Wantland
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 176-200
Technical Paper | Fuel | doi.org/10.13182/NT74-A31474
Thermal and Irradiation Effects on the Tensile and Creep-Rupture Properties of Weld-Deposited Type 316 Stainless Steel
A. L. Ward
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 201-215
Technical Paper | Material | doi.org/10.13182/NT74-A31475
Dispersion-Strengthened Ferritic Steels as Fast-Reactor Structural Materials
J.-J. Huet, V. Leroy+
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 216-224
Technical Paper | Material | doi.org/10.13182/NT74-A31476
The Kinetics of Decarburization of Cr —1% Mo Steel in Sodium
J. L. Krankota, J. S. Armijo
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 225-233
Technical Paper | Material | doi.org/10.13182/NT74-A31477
The Viscosity of UO2-Basalt Melts
L. Leibowitz, C. Williams, M. G. Chasanov
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 234-237
Technical Paper | Material | doi.org/10.13182/NT74-A31478
Radiation Doses from Hypothetical Exposures to Combustion Products of Plowshare Gas Discharged from Stacks
R. E. Moore, C. J. Barton
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 238-245
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT74-A31479
Nondestructive Burnup Determination by Gamma-Ray Spectroscopy
C. K. Tzou, C. M. Yang
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 246-251
Technical Paper | Analysis | doi.org/10.13182/NT74-A31480
The Application of Post-Cutting Chip Activation Analysis to the Study of Tool Wear
K. N. Prasad, W. A. Jester, F. J. Remick
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 252-259
Technical Paper | Analysis | doi.org/10.13182/NT74-A31481
United States Atomic Energy Waste Management Programs and Objectives
Frank K. Pittman
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 273-285
Technical Paper | Keynote Paper | doi.org/10.13182/NT74-A31487
The Hidden Commitment of Nuclear Wastes
William D. Rowe, William F. Holcomb
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 286-293
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31488
Waste Management — Licensing and Criteria
S. H. Smiley
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 294-299
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31489
Management of Radioactive Wastes — Programs of the International Atomic Energy Agency
Donald G. Jacobs
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 300-304
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31490
Radioactive Waste Management in Selected Foreign Countries
H. M. Parker
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 305-308
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31491
Cost/Benefit Considerations of Nuclear Power
Richard L. Rudman
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 309-313
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31492
Nuclear Radiation—Sources and Impact
Carl M. Unruh
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 314-322
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31493
Nuclear Fuel Cycle and the Isotopic Compositions
Joseph A. Angelo, Jr., Roy G. Post
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 323-330
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31494
Evaluation Methodology of Waste Management Concepts
D. E. Deonigi
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 331-338
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31495
Handling and Packaging of Plutonium-Contaminated Waste
J. B. Owen
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 339-342
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31496
Transportation of Nuclear Fuel and Waste
William Brobst
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 343-355
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31497
Geohydrologic Considerations in the Management of Radioactive Waste
George D. DeBuchananne
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 356-361
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31498
Methods for Removal of Actinides From High-Level Wastes
W. D. Bond, H. C. Claiborne, R. E. Leuze
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 362-370
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31499
High-Level Waste Solidification: Applicability of Fluidized-Bed Calcination to Commercial Wastes
B. R. Dickey, B. R. Wheeler, J. A. Buckham
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 371-382
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31500
ITSA—Above-Ground Retrievable Storage Method for Low-Level Transuranic Wastes
Paul J. Macbeth, Winston W. Hickman
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 383-390
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31501
Retrievable Surface Storage Facility for Commercial High-Level Waste
Dean C. Nelson, Donald D. Wodrich
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 391-397
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31502
Disposal of Radioactive Waste in Bedded Salt Formations
William C. McClain, A. L. Boch
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 398-408
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31503
The Management of Spent CANDU fuel
W. W. Morgan
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 409-417
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31504
Extraterrestrial Disposal of Nuclear Wastes
Kirk Drumheller
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 418-424
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31505
Seabed Disposal — Where to Look
W. P. Bishop, C. D. Hollister
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 425-443
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31506
Chemical Behavior and Ground Movement of Selected Radionuclides
A. E. Smith, D. J. Brown, R. E. Isaacson
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 444-446
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31507
Measuring Radioactivity in the Environment — The Quality of the Data
Arthur N. Jarvis, David G. Easterly
Nuclear Technology | Volume 24 | Number 3 | December 1974 | Pages 447-450
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31508
