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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
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Dryout of an Inductively Heated Bed of Steel Particles with Subcooled Flow from Beneath the Bed
F. P. Tsai, J. Jakobsson, I. Catton, V. K. Dhir
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 10-15
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33367
Modes of Heat Removal from a Heat-Generating Debris Bed
D. Squarer, L. E. Hochreiter, A. T. Pieczynski
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 16-22
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33368
On the Pattern of Water Penetration into a Hot Particle Bed
D. H. Cho, Donn R. Armstrong II, S. H. CHAN
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 23-31
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33369
Radiative Contribution to the Heat Transfer in Liquid Urania
M. Bober, J. Singer, K. Wagner
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 32-35
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33370
On the Location and Mechanisms of Dryout in Top-Fed and Bottom-Fed Particulate Beds
G. Hofmann
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 36-45
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33371
Mechanical Behavior of SNR-300 Reactor Vessel Components Under Postaccident Heat Removal Conditions
Hartwig Laue, Klaus Hermann Kerz
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 46-52
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33372
A Coolability Model for Postaccident Nuclear Reactor Debris
Ronald J. Lipinski
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 53-66
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33373
Cooling of Debris Beds
Leopold Barleon, Klaus Thomauske, Heinrich Werle
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 67-86
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33374
Light Water Reactor Debris from Severe In-Pile Transient Tests
Richard R. Hobbins, Beverly A. Cook, Richard E. Mason
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 87-91
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33375
Steam Generator Leak Detection in Liquid-Metal Fast Breeder Reactors by Chemical Methods
George J. Licina, Dwight R. Springer, Prodyot Roy
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 92-101
Technical Paper | Postaccident Debris Cooling / Nuclear Safety | doi.org/10.13182/NT84-A33376
Nonsoluble Fission Product Residues, Crud, and Fine Chips of Zircaloy Cladding in Headend Process of Nuclear Fuel Reprocessing
Kozo Gonda, Koichiro Oka, Keiichi Hayashi
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 102-108
Technical Paper | Postaccident Debris Cooling / Fuel Cycle | doi.org/10.13182/NT84-A33377
Chemical Interactions Between UO2 and Zircaloy-4 from 1000 to 2000°C
Wolfgang Dienst, Peter Hofmann, Deborah K. Kerwin-Peck
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 109-124
Technical Paper | Postaccident Debris Cooling / Nuclear Fuel | doi.org/10.13182/NT84-A33378
On the Applicability of Analytical Solutions of the Transport Equation for the Migration of Substances in Groundwater-Bearing Horizons
Marion Petschel, Dietmar Zappe
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 125-130
Technical Paper | Postaccident Debris Cooling / Radioactive Waste Management | doi.org/10.13182/NT84-A33379
The Effect of Composition of Selected Groundwaters from the Basin and Range Province on Plutonium, Neptunium, and Americium Speciation
Terry F. Rees, Jess M. Cleveland, Kenneth L. Nash
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 131-137
Technical Paper | Postaccident Debris Cooling / Radioactive Waste Management | doi.org/10.13182/NT84-A33380
Investigation of Oxides Formed in the Corrosion of SUS-304 in High-Temperature Water Through the Measurement of Evolved Hydrogen and Radiochemical Analyses
Enzo Tachikawa, Michio Hoshi, Chiaki Sagawa, Chushiro Yonezawa, Mikio Nakashima
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 138-145
Technical Paper | Postaccident Debris Cooling / Material | doi.org/10.13182/NT84-A33381
Scaling Criteria for Two-Phase Flow Loops and Their Application to Conceptual 2×4 Simulation Loop Design
Gunol Kocamustafaogullari, Mamoru Ishii
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 146-160
Technical Paper | Postaccident Debris Cooling / Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33382
Paint Decontamination Kinetics
Edward W. Thornton
Nuclear Technology | Volume 65 | Number 1 | April 1984 | Pages 161-167
Technical Paper | Postaccident Debris Cooling / Technique | doi.org/10.13182/NT84-A33383
Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors
Leon C. Walters, B. R. Seidel, J. Howard Kittel
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 179-231
Critical Review | doi.org/10.13182/NT84-A33408
Risk-Oriented Analysis of the German Prototype Fast Breeder Reactor SNR-300: Off-Site Accident Consequence Model and Results of the Study
Anton Bayer, Joachim Ehrhardt
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 232-249
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33409
An Investigation of BWR/4 Parallel Channel Effects During a Hypothetical Loss-of-Coolant Accident for Both Intact and Broken Jet Pumps
Mohammad R. Fakory, R. T. Lahey, Jr.
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 250-265
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33410
Vapor Transport of Fission Products in Postulated Severe Light Water Reactor Accidents
Daniel Cubicciotti, Bal Raj Sehgal
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 266-291
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33411
Optimization and Analysis of Low-Leakage Core Management for Pressurized Water Reactors
Yi-Chiang Chang, Alexander Sesonske
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 292-304
Technical Paper | Fuel Cycle | doi.org/10.13182/NT84-A33412
Recovery of Noble Metals from Fission Products
George A. Jensen, A. M. Platt, George B. Mellinger, William J. Bjorklund
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 305-324
Technical Paper | Chemical Processing | doi.org/10.13182/NT84-A33413
Application of Dynamic Simulation to Radwaste Evaporator Systems
Habib Amin, K. C. Chiu, David W. James
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 325-331
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33414
Using Titanium Oxide for Cobalt Removal from High-Temperature Water
Fumio Kawamura, Kiyomi Funabashi, Makoto Kikuchi, Katsumi Ohsumi
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 332-339
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33415
A Multiple Regression Equation for Calculated keff Bias Errors by Criticality Code System
Yasushi Nomura, Takanori Shimooke
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 340-349
Technical Paper | Criticality Safety | doi.org/10.13182/NT84-A33416
Technique for Producing a Continuous Interference-Free Stream of Argon-41 in Air
Tung-Tse Tseng, William A. Jester
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 350-353
Technical Note | Analyse | doi.org/10.13182/NT84-A33417
Core Stability Test Analysis Using the Autoregressive Model
Tohru Mitsutake, Shigeaki Tsunoyama, Shigeru Kanemoto, Hideaki Namba, Shirley A. Sandoz
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 365-373
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33391
Reactor Core Stability Analysis for a Boiling Water Reactor by a Transient Model
Shigeaki Tsunoyama, Tohru Mitsutake, Shigeo Ebata, Shirley A. Sandoz
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 374-382
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33392
Automated Control Rod Programming in Boiling Water Reactor Cores
Wan-Li Zhong, J. Weisman
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 383-394
Technical Paper | Fission Reactor | doi.org/10.13182/NT84-A33393
Development of a Sodium Vapor Pressure Meter Using Beta-Alumina Ceramics
Susumu Ninomiya, Fumio Ohtsuka, Hiromichi Nei, Osamu Takikawa, Mituo Harata
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 395-401
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33394
Electrically Enhanced Deposition of a Confined Aerosol in the Presence of Ionizing Radiation
Robert A. FJeld, Thomas J. Overcamp
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 402-408
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33395
Analysis of Coolant Pressure Fluctuation and Induced Vibration of Liquid-Metal Fast Breeder Reactor Fuel Pins
Ken Amano, Kotaro Inoue
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 409-414
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33396
Dominant Factors in the Release of Fission Products from Overheated Urania
C. D. Andriesse, R. H. J. Tanke
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 415-421
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33397
Leach Testing of Idaho National Engineering Laboratory Waste Forms in a Gamma Field
Robert P. Schuman
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 422-431
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33398
The Leaching Behavior of Zircaloy Cladding and Its Impact on the Conditioning of Waste for Final Disposal
Berthold-Günter Brodda, Erich Richard Merz
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 432-437
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33399
Radioactive Contamination of Carbon Steel in a Boiling Water Reactor
Takashi Honda, Akira Minato, Katsumi Ohsumi, Hideo Matsubayashi
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 438-443
Technical Paper | Material | doi.org/10.13182/NT84-A33400
Hydraulics of Blocked Rod Bundles
Shi-Chune Yao, M. J. Loftus, L. E. Hochreiter
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 444-453
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33401
An Improved Multidimensional Finite Difference Scheme for Predicting Stratified Horizontal Pipe Flow
Yassin A. Hassan, James G. Rice, Jong H. Kim
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 454-461
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT84-A33402
Comparative Study of Measurements by Means of Gamma Thermometer Strings with Fission Chamber Measurements
Charles Hantouche
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 462-466
Technical Note | Fission Reactor | doi.org/10.13182/NT84-A33403
