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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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Latest News
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
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High-Strength High-Efficiency Particulate Air Filters for Nuclear Applications
Volker Rüdinger, Craig I. Ricketts, Jürgen G. Wilhelm
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 11-29
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Nuclear Safety | doi.org/10.13182/NT90-A34483
Application of Circular Filter Inserts
R. P. Pratt, B. L. Stewart, D. Loughborough
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 30-39
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Radioactive Waste Management | doi.org/10.13182/NT90-A34484
Filtered Venting for German Power Reactors
H.-G. Dillmann, H. Pasler, J. G. Wilhelm
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 40-49
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Nuclear Safety | doi.org/10.13182/NT90-A34485
Aspects of the Increase in Pressure Drop of High-Efficiency Particulate Air Filters Under Fog Conditions
Craig I. Ricketts, Volker Rüdinger, Jürgen G. Wilhelm
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 50-65
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Nuclear Safety | doi.org/10.13182/NT90-A34486
Off-Gas Cleaning in an FRG Reprocessing Plant
Jürgen Furrer, Walter Weinländer
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 66-76
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Radiation Biology and Environment | doi.org/10.13182/NT90-A34487
Conceptual Design of a Medical Reactor for Neutron Capture Therapy
William A. Neuman, James L. Jones
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 77-92
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Fission Reactor | doi.org/10.13182/NT90-A34488
Power Flattening in a Catalyzed Deuterium-Deuterium Fusion-Driven Hybrid Blanket Using Nuclear Waste Actinides
Sümer Şahın
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 93-105
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Fission Reactor | doi.org/10.13182/NT90-A34489
Epithermal Neutron Beam Design for Neutron Capture Therapy at the Power Burst Facility and the Brookhaven Medical Research Reactor
Floyd J. Wheeler, D. Kent Parsons, Brian L. Rushton, David W. Nigg
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 106-117
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Fission Reactor | doi.org/10.13182/NT90-A34490
An Automatic Control Rod Programming Method for a Boiling Water Reactor
Chaung Lin
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 118-126
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Radioactive Waste Management | doi.org/10.13182/NT90-A34491
A 3He++ Radio-Frequency Quadrupole Accelerator for Positron Emission Tomography
Ali E. Dabiri, William K. Hagan, Donald A. Swenson, Kenneth A. Krohn
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 127-133
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Radioisotopes and Isotope Separation | doi.org/10.13182/NT90-A34492
Analysis of a Fluid-Mechanic Model of a Horizontal Tee-Junction
Yin-Pang Ma, Bau-Shei Pei, Wei-Keng Lin, Yih-Yun Hsu
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 134-140
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34493
Analysis of a Nuclear Power Plant Using RELAP5/MOD2 with Modified Bundle Heat Transfer Correlations
Yassin A. Hassan, Parvez Salim
Nuclear Technology | Volume 92 | Number 1 | October 1990 | Pages 141-149
Technical Paper | Development of Nuclear Gas Cleaning and Filtering Techniques / Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34494
Modification of a Mobile Nuclear Reactor for Medical Diagnosis
Chien Chung, Chen-Yi Chen
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 159-166
Technical Paper | Fission Reactor | doi.org/10.13182/NT90-A34467
State Feedback Assisted Classical Control: An Incremental Approach to Control Modernization of Existing and Future Nuclear Reactors and Power Plants
Robert M. Edwards, Kwang Y. Lee, M. A. Schultz
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 167-185
Technical Paper | Fission Reactor | doi.org/10.13182/NT90-A34468
A Random Sampling Discrete Probability Algorithm with Condensation for Probabilistic Analysis
Robert E. Kurth, David C. Cox
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 186-193
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34469
RELAP5/MOD2 Analysis of N Reactor Cold-Leg Manifold Break Transient Without Scram
K. Sathyanarayana, Donald M. Ogden
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 194-203
Technical Paper | Nuclear Safety | doi.org/10.13182/NT90-A34470
Fission Product Release from Spent UO2 Fuel Under Uranium-Saturated Oxic Conditions
Bernd Grambow, R. S. Forsyth, Lars O. Werme, Jordi Bruno
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 204-213
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34471
Fission Product Release and Fuel Behavior of Irradiated Light Water Reactor Fuel Under Severe Accident Conditions: The ST-1 Experiment
Michael D. Allen, Harlan W. Stockman, Kenneth O. Reil, Arthur J. Grimley
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 214-228
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT90-A34472
Guidelines for Quality Assurance and Quality Control of Radioactive Wastes
Ernst Warnecke, Dietmar Bröcking, Peter Podewils
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 229-237
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT90-A34473
Modeling on Evaporation Characteristics of a Reprocessing Plant High-Level Liquid Waste Concentrator
Masanori Takahashi, Tatsuo Izumida, Fumio Kawamura, Hideo Yusa
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 238-242
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT90-A34474
Studies of the Decomposition of Sodium Carbonate in High-Temperature Sodium
S. Rajendran Pillai, R. Ranganathan, Cherian K. Mathews
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 243-247
Technical Paper | Material | doi.org/10.13182/NT90-A34475
Heat Transfer Modeling in Low Flows and Application to Reflood Heat Transfer
John C. Statharas, John G. Bartzis, Demosthenes D. Papailiou
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 248-259
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34476
Study of a Natural-Circulation Boiling Water Reactor with Passive Safety
Hideo Nagasaka, Takashi Sato, Hirohide Oikawa, Ryoichi Hamazaki, Kenji Arai, Takao Kageyama, Hiroyuki Yoshida, Hiroshi Machiba
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 260-268
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34477
Thermal Hydraulics During Boiling in Thermosyphon Evaporators
D. P. Pande, P. L. Dhar, R. S. Agarwal, R. V. Amalraj
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 269-281
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A34478
An Empirical Calculational Procedure for Beta-Particle Escape Efficiency in Delayed Self-Powered Neutron Detectors
M. N. Agu
Nuclear Technology | Volume 92 | Number 2 | November 1990 | Pages 282-283
Technical Note | Analyse | doi.org/10.13182/NT90-A34479
Development of Generic In-Service Inspection Priorities for Pressure Boundary Systems
Truong V. Vo, Brian W. Smith, Frederic A. Simonen, Steven R. Doctor
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 291-299
Technical Paper | Fission Reactor | doi.org/10.13182/NT90-A16231
Instrumentation and Control Revamping
Jean-Lucien Mourlevat, Alain Parry, Jean-François Petetrot, Jean-François Aschenbrenner
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 300-308
Technical Paper | Fission Reactor | doi.org/10.13182/NT90-A16232
Development and Validation of a Steam Generator Simulation Model
Mankit Ray Yeung, Ping Lam Chan
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 309-314
Technical Paper | Fission Reactor | doi.org/10.13182/NT90-A16233
Release of Iodine and Noble Gas Fission Products from Defected Fuel Elements During Reactor Shutdown and Start-Up
Brent J. Lewis, Roderick D. MacDonald, Hugues W. Bonin
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 315-324
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT90-A16234
Behavior of Modern Metallic Fuel in TREAT Transient Overpower Tests
Theodore H. Bauer, Arthur E. Wright, William R. Robinson, John W. Holland, Edgar A. Rhodes
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 325-352
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT92-325
A Model for Fission Gas Release and Fuel Oxidation Behavior for Defected UO2 Fuel Elements
Brent J. Lewis, Fernando C. Iglesias, David S. Cox, Elena Gheorghiu
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 353-362
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT90-A16236
Modeling of a Diffusion-Sorption Experiment by Linear and Nonlinear Sorption Isotherms
Paul A. Smith
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 363-373
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT90-A16237
Calculation of Calibration Factors and Layout Criteria for Gamma Scanning of Waste Drums from Nuclear Plants
Wilhelm in der Schmitten, Bernd Sohnius, Erwin Wehner
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 374-382
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT90-A16238
Yield Stress Determination by the Massachusetts Institute of Technology Miniaturized Disk Bend Test
Dong-Seong Sohn, Gordon E. Kohse, David M. Parks, Otto K. Harling
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 383-388
Technical Paper | Material | doi.org/10.13182/NT90-A16239
Practical Methods of Measuring Dimensions from Neutron Radiographs of Nuclear Reactor Fuel
Jozef C. Domanus
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 389-395
Technical Paper | Radiation Application | doi.org/10.13182/NT90-A16240
The Investigation of Conjugate Heat Transfer Phenomena in Advanced Fast Reactors
T. C. Hung, V. K. Dhir
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 396-410
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT90-A16241
An Integrated Signal Validation System for Nuclear Power Plants
Keith E. Holbert, Belle R. Upadhyaya
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 411-427
Technical Paper | Instrumentation and Control | doi.org/10.13182/NT90-A16242
