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Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
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A New Expression of Few-Group Nuclear Constants for Analyzing Light Water Reactor Cores
Y. Naito, M. Mimura, M. Toba, R. Onuki
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 7-20
Technical Paper | Reactor | doi.org/10.13182/NT79-A32375
Correlation of the Cesium-134/Cesium-137 Ratio to Fast Reactor Burnup
John R. Phillips, Barry K. Barnes, Thomas R. Bement
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 21-29
Technical Paper | Reactor | doi.org/10.13182/NT46-21
Molten-Salt Reactors for Efficient Nuclear Fuel Utilization Without Plutonium Separation
J. R. Engel, W. A. Rhoades, W. R. Grimes, J. F. Dearing
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 30-43
Technical Paper | Reactor | doi.org/10.13182/NT79-A32377
A Simplified Interassembly Heat Transfer Model for the Analysis of Liquid-Metal Fast Breeder Reactor Core Restraint Systems
Jim P. Wei
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 44-52
Technical Paper | Reactor | doi.org/10.13182/NT79-A32378
A Method for Refueling Light Water Reactors with Natural Uranium
Yigal Ronen
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 53-60
Technical Paper | Reactor | doi.org/10.13182/NT79-A32379
Power Supply Requirements for a Tokamak Fusion Reactor
Jeffrey N. Brooks, Robert L. Kustom
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 61-81
Technical Paper | Reactor | doi.org/10.13182/NT79-A32380
Sensitivity of Nuclear Fuel Cycle Cost to Uncertainties in Nuclear Data
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 82-97
Technical Paper | Fuel Cycle | doi.org/10.13182/NT79-A32381
An Automated Gravimetric Titrator for the Determination of Uranium in Safeguards Materials
Bruce W. Moran
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 98-104
Technical Paper | Fuel Cycle | doi.org/10.13182/NT79-A32382
Comparison of Anion Exchange Resins for Recovering Plutonium from Nitric Acid Waste
J. D. Navratil, L. L. Martella
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 105-109
Technical Paper | Chemical Processing | doi.org/10.13182/NT79-A32383
The Effect of Solid Fission Products and Dislocations on Oxide Fuel Element Behavior in Fast Overpower Transients
Shan Heng Chien, A. R. Wazzan, D. Okrent
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 110-126
Technical Paper | Fuel | doi.org/10.13182/NT79-A32384
Radiation-Induced Outgassing from Type 304 Stainless Steel
T. P. Toepker, J. N. Anno
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 127-133
Technical Paper | Material | doi.org/10.13182/NT79-A32385
Observations of Dilation and Bowing in Experimental Breeder Reactor II Ducts and Cladding
L. C. Walters, C. M. Walter
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 134-148
Technical Paper | Material | doi.org/10.13182/NT79-A32386
Dynamics and Control of a Packed Distillation Column for the Isotopic Enrichment of Plasma Exhausts from Controlled Thermonuclear Reactors
James F. Davis, Richard S. H. Mah, William F. Stevens, Balabhadra Misra, Victor A. Maroni
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 149-158
Technical Paper | ISotopes Separation | doi.org/10.13182/NT79-A32387
Numerical Simulation of the Baneberry Event
R. W. Terhune, H. D. Glenn, D. E. Burton, H. L. McKague, J. T. Rambo
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 159-169
Technical Paper | Nuclear Explosive | doi.org/10.13182/NT79-A32388
Flow Behavior of Volume-Heated Boiling Pools: Implications with Respect to Transition Phase Accident Conditions
T. Ginsberg, O. C. Jones, Jr., J. C. Chen
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 391-398
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32344
Determination of the Sources of the Airborne Physico-Chemical Iodine-131 Species in a Pressurized Water Reactor Power Plant
H. Deuber, J. G. Wilhelm
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 399-403
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32345
Fission Product Source Terms for the Light Water Reactor Loss-of-Coolant Accident
R. A. Lorenz, J. L. Collins, A. P. Malinauskas
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 404-410
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32346
TRAC Analysis of Loss-of-Fluid Test Non-Nuclear Test L1-4
J. J. Pyun, K. A. Williams
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 411-421
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32347
Analysis of a Simulated Small Break in the Semiscale System Under Loss-of-Coolant Accident Conditions
Charles E. Cartmill
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 422-427
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32348
Coupled Vibrations of a Structure and Fluid Excited by Pressure Shocks
Jorma Arros
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 428-432
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32349
Vent Clearing During a Simulated Loss-of-Coolant Accident in a Mark I Boiling Water Reactor Pressure-Suppression System
J. H. Pitts, E. W. McCauley
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 433-441
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32350
Damage Mechanisms to Cables in Reactor Loss-of-Coolant Accident Environments
R. E. Leadon, N. A. Lurie
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 442-446
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32351
Thermal-Hydraulic Analysis of Fuel Blockages Formed During Transient Overpower Accidents in Liquid-Metal Fast Breeder Reactors
V. K. Dhir, W. E. Kastenberg, D. W. Varela
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 447-452
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32352
Comparative Study of Heterogeneous and Homogeneous Liquid-Metal Fast Breeder Reactor Cores in Some Accident Conditions
A. Renard, G. Evrard, U. Wehmann
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 453-464
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32353
Rod Bundle Critical Heat Flux at Low Pressure
Robert P. Wadkins, Richard G. Ambrosek, Michael W. Young
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 465-472
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32354
Reflood Heat Transfer Correlation
Hsu-Chieh Yeh, Cleon E. Dodge, Lawrence E. Hochreiter
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 473-481
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32355
Fuel-Coolant Interactions in a Shock Tube Geometry
A. Segev, R. E. Henry, S. G. Bankoff
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 482-492
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32356
Higher Order Effects in Calculating Boiling Water Reactor Doppler and Void Reactivity Feedback
David J. Diamond, Hsiang-Shou Cheng
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 493-499
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32357
Safety Aspects of Using Gadolinium as Burnable Poison in Pressurized Water Reactors
Cl. Vandenberg, H. Bonet, A. Charlier, F. Motte
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 500-506
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32358
Space-Time Neutronic Analysis of Postulated Loss-of-Coolant Accidents in CANDU Reactors
J. C. Luxat, G. M. Frescura
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 507-516
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32359
A Critical Experimental Study of Integral Physics Parameters in Simulated Liquid-Metal Fast Breeder Reactor Meltdown Cores
S. K. Bhattacharyya, D. C. Wade, R. G. Bucher, D. M. Smith, R. D. McKnight, L. G. LeSage
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 517-524
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32360
Low Sodium Void Cores
W. P. Barthold, J. C. Beitel, P. S. K. Lam, Y. Orechwa, S. F. Su, R. B. Turski
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 525-528
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32361
Pressure Field and Core Barrel Loadings During Pressurized Water Reactor Blowdown
G. Enderle, F. Katz, H. Mösinger, E. G. Schlechtendahl, K. Stölting
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 529-535
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32362
Application of Fluid-Structure Interaction for Steam Generator Force Analysis
D. J. Kowalski, V. J. Esposito
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 536-539
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32363
Two-Phase Critical Flow in Long Nozzles
J. Y. Boivin
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 540-545
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32364
Analytical Simulations in the Field of Two-Phase Flow: A Promising Scaling Law for the Interpretation of Experiments
H. Karwat
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 546-558
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32365
Release of Fission and Activation Products During Light Water Reactor Core Meltdown
H. Albrecht, V. Matschoss, H. Wild
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 559-565
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32366
Radioactivity Release Versus Probability for a Steam Generator Tube Rupture Accident
A. J. Buslik, R. E. Hall
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 566-570
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32367
Fission Product Release from a Pressurized Water Reactor Defective Fuel Rod: Effect of Thermal Cycling
Gerard Kurka, Alain Harrer, Pierre Chenebault
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 571-581
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32368
LMFBR Steam Generators: Behavior of Heat Exchange Tubes Faced with a Through Crack Resulting in Contact Between Sodium and Water
J. L. Quinet, L. Lannou
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 582-590
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32369
Fuel Pins and Core Response Under Liquid-Metal Fast Breeder Reactor Transient Overpower Accident Conditions
N. P. Wilburn, D. E. Smith, R. E. Baars, D. B. Atcheson,, B. W. Spencer
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 591-599
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32370
An Analysis of Transient Overpower Accidents in the Fast Test Reactor Using the Los Alamos Failure Model
Peter K. Mast, James H. Scott
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 600-605
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32371
Safety Aspects of Light Water Reactor Radwaste Solidification Processes
L. Mergan, J. Storrer, R. Verbeke, J. P. Cordier
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 606-610
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32372
Common-Mode Failures in Redundancy Systems
I. A. Watson, G. T. Edwards
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 183-191
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32315
The Behavior of Concrete in Contact with Molten Corium in the Case of a Hypothetical Core Melt Accident
Martin Peehs, Alfred Skokan, M. Reimann
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 192-198
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT46-192
Test Prediction for the German PKL Test K5A Using RELAP4/MOD6
Yi-Shung Chen, William S. Haigh, L. Harold Sullivan, Stewart R. Fischer
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 199-204
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32317
Parameter Study on the Influence of Prepressurization on PWR Fuel Rod Behavior During Normal Operation and Hypothetical LOCAs
B. Brzoska, F. Depisch, H. P. Fuchs, W. Sauermann
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 205-212
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32318
Comparisons Between Measured and FRAP-T4-Predicted Fuel Rod Failure Probability Under Pellet-Cladding Interaction Conditions
Dennis R. Coleman
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 213-219
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32319
The Axial Distribution of Deformation in the Cladding of Pressurized Water Reactor Fuel Rods in a Loss-of-Coolant Accident
K. M. Rose, C. A. Mann, E. D. Hindle
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 220-227
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32320
Failure Mechanisms and Fission Product Release in High-Temperature Gas-Cooled Reactor Fuel Under Conditions of Unrestricted Core Heatup Events
W. Schenk, A. Naoumidis
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 228-233
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32321
Modes of Failure of Fast Reactor Fuel Pins Irradiated Under Loss-of-Coolant-Flow Conditions
H. Kwast
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 234-240
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32322
An On-Line Meteorological Information System for Response to Accidental Releases of Radioactivity into the Atmosphere
Helmut Peter Thomas
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 241-247
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32323
Radionuclide Transport in Soil—Description and Application of a Calculational Model
K. Schwarzer
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 248-254
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32324
Chemical Reactions Between Light Water Reactor Core Melt and Concrete
Alfred Skokan, Helmut Holleck, Martin Peehs
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 255-262
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32325
Modeling of Equiaxed Grain Growth in Uranium Dioxide Fuels
William L. Baldewicz, Ahmed R. Wazzan, David Okrent
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 263-267
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32326
A New Approach for Rod-Bundle Thermal-Hydraulic Analysis
W. T. Sha, H. M. Domanus, R. C. Schmitt, J. J. Oras, E. I. H. Lin, V. L. Shah
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 268-280
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32327
Investigation of Local Cooling Disturbances in an In-Pile Sodium Loop in the BR2
W. Kramer, K. Schleisiek, L. Schmidt, G. Vanmassenhove, A. Verwimp
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 281-288
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32328
Considerations on Incoherency of Boiling and Voiding in Liquid-Metal Fast Breeder Reactor Subassemblies During a Loss-of-Flow Accident
R. Nijsing, W. Eifler
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 289-299
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32329
The Influence of Meteorological Parameters on the Consequences of Accidental Activity Releases from Nuclear Power Plants
Siegfried Vogt, Wolfgang G. Hübschmann
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 300-305
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32330
The Fission Product Retention of Pebble-Bed Reactors in Ultimate Accidents
K. Petersen, H. Barthels, H. E. Drescher, C. B. Von Der Decken, N. Iniotakis, W. Schenk, R. Schulten
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 306-311
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32331
Tritium Contamination of the Product Gas in a High-Temperature Reactor Heated Process Plant
W. Steinwarz, H. J. Cordewiner, H. D. Röhrig
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 312-317
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32332
Controlling Cesium in the Coolant of the Experimental Breeder Reactor II
W. H. Olson, W. E. Ruther
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 318-322
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32333
A Revised ANS Standard for Decay Heat from Fission Products
Virgil E. Schrock
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 323-331
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32334
Attenuation of Airborne Debris from Liquid-Metal Fast Breeder Reactor Accidents
H. A. Morewitz, R. P. Johnson, C. T. Nelson, E. U. Vaughan, C. A. Guderjahn, R. K. Hilliard, J. D. McCormack, A. K. Postma
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 332-339
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32335
Steam-Water Mixing in Nuclear Reactor Safety Loss-of-Coolant Experiments
Samuel A. Naff, William F. Schwarz
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 340-343
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32336
In-Reactor Experiments on the Cooling of Fast Reactor Debris
J. B. Rivard
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 344-349
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32337
Acoustic Measurement of the Penetration of a Molten Metallic Pool into Concrete
Herbert J. Sutherland
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 350-355
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32338
Dryout Heat Fluxes in Debris Beds Cooled at the Bottom and Having Subcooled Liquid at the Top
Vijay K. Dhir, Ivan Catton
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 356-361
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32339
Multichannel Model for Fuel-Coolant Interaction in a Liquid-Metal Fast Breeder Reactor Subassembly
Kent Mehr, Heinz M. Kottowski, Horst Goldammer
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 362-368
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32340
A Theoretical Study of Reinforced Concrete Structures Under Missile Impact Loading
Vladislav Adamík
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 369-377
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32341