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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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Criticality Safety Analysis of a Calciner Exit Chute
C. F. Haught, B. Basoglu, R. W. Brewer, D. F. Hollenbach, A. D. Wilkinson, H. L. Dodds, R. L. Oxenham
Nuclear Technology | Volume 105 | Number 1 | January 1994 | Pages 3-13
Technical Paper | Special on Nuclear Criticality Safety / Nuclear Criticality Safety | doi.org/10.13182/NT94-A34906
Simulation of Hypothetical Criticality Accidents Involving Homogeneous Damp Low-Enriched UO2 Powder Systems
B. Basoglu, R. W. Brewer, C. F. Haught, D. F. Hollenbach, A. D. Wilkinson, H. L. Dodds, P. F. Pasqua
Nuclear Technology | Volume 105 | Number 1 | January 1994 | Pages 14-30
Technical Paper | Special on Nuclear Criticality Safety / Nuclear Criticality Safety | doi.org/10.13182/NT94-A34907
Modeling of Central Reactivity Worth Measurements in Lady Godiva
Tracy R. Wenz, Robert D. Busch
Nuclear Technology | Volume 105 | Number 1 | January 1994 | Pages 31-36
Technical Note | Special on Nuclear Criticality Safety / Nuclear Criticality Safety | doi.org/10.13182/NT94-A34908
TRIGA Mark II Benchmark Experiment, Part I: Steady-State Operation
Irena Mele, Matjaž Ravnik, Andrej Trkov
Nuclear Technology | Volume 105 | Number 1 | January 1994 | Pages 37-51
Technical Paper | Special on Nuclear Criticality Safety / Fission Reactor | doi.org/10.13182/NT94-A34909
TRIGA Mark II Benchmark Experiment, Part II: Pulse Operation
Nuclear Technology | Volume 105 | Number 1 | January 1994 | Pages 52-58
Technical Paper | Special on Nuclear Criticality Safety / Fission Reactor | doi.org/10.13182/NT94-1
The Quenching of Hydrogen/Air Flames in Obstructed and Multicompartment Configurations by Partial Inertization
Johan G. Visser, W. Paul M. Mercx, George L. C. M. Vayssier
Nuclear Technology | Volume 105 | Number 1 | January 1994 | Pages 59-69
Technical Paper | Special on Nuclear Criticality Safety / Nuclear Reactor Safety | doi.org/10.13182/NT94-A34911
Transient Analysis and Startup Simulation of a Thermionic Space Nuclear Reactor System
Mohamed S. El-Genk, Huimin Xue, Dmitry Paramonov
Nuclear Technology | Volume 105 | Number 1 | January 1994 | Pages 70-86
Technical Paper | Special on Nuclear Criticality Safety / Nuclear Reactor Safety | doi.org/10.13182/NT94-A34912
On the Use of Expert Judgments to Estimate the Pressure Increment in the Sequoyah Containment at Vessel Breach
Sumeet Chhibber, George E. Apostolakis, David Okrent
Nuclear Technology | Volume 105 | Number 1 | January 1994 | Pages 87-103
Technical Paper | Special on Nuclear Criticality Safety / Nuclear Reactor Safety | doi.org/10.13182/NT94-A34913
Conceptual Design Loss-of-Coolant Accident Analysis for the Advanced Neutron Source Reactor
N. C. J. Chen, Mark W. Wendel, Graydon L. Yoder, Jr.
Nuclear Technology | Volume 105 | Number 1 | January 1994 | Pages 104-122
Technical Paper | Special on Nuclear Criticality Safety / Nuclear Reactor Safety | doi.org/10.13182/NT94-A34914
An Experimental Study of Gravity-Driven Countercurrent Two-Phase Flow in Horizontal and Inclined Channels
K. H. Lillibridge, S. M. Ghiaasiaan, S. I. Abdel-Khalik
Nuclear Technology | Volume 105 | Number 1 | January 1994 | Pages 123-134
Technical Paper | Special on Nuclear Criticality Safety / Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34915
Interaction of Iodine with Preoxidized Stainless Steel
J. Abrefah, H. F. G. De Abreu, F. Tehranian, Y. S. Kim, D. R. Olander
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 137-144
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34918
Incipient Fault Detection and Identification in Process Systems Using Accelerated Neural Network Learning
Alexander G. Parlos, Jayakumar Muthusami, Amir F. Atiya
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 145-161
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34919
TRACG Transient Analysis Code—Three-Dimensional Kinetics Model Implementation and Applicability for Space-Dependent Analysis
Yutaka Takeuchi, Yukio Takigawa, Hitoshi Uematsu, Shigeo Ebata, James C. Shaug, Bharat S. Shiralkar
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 162-183
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34920
The Optimization of Squared-Off Cascades for Isotope Separation
Chuntong Ying, Edward Von Halle
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 184-189
Technical Paper | Enrichment and Reprocessing | doi.org/10.13182/NT94-A34921
Scaling Laws and Design Aspects of a Natural-Circulation-Cooled Simulated Boiling Water Reactor Fuel Assembly
Rudi Van De Graaf, T. H. J. J. Van Der Hagen, Robert F. Mudde
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 190-200
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34922
Similarity of Two-Fluid Flow Heated by a Fuel Rod
Sandor Benedek
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 201-215
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34923
An Assessment of the Critical Heat Flux Approaches of Thermal-Hydraulic System Analysis Codes Using Bundle Data from the Heat Transfer Research Facility
Min Lee, Lih-Yih Liao
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 216-230
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34924
A Modeling Study of the PMK-NVH Integral Test Facility
Borut Mavko, Iztok Parzer, Stojan Petelin
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 231-252
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34925
On a Simplified Two-Phase Slug Flow Model
Yu-Wen Wang, Bau-Shei Pei, Wei-Keng Lin
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 253-260
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34926
The Effect of Dissolved Gas Bubble Nucleation on Natural Convection Heat Transfer in Narrow Channels
Wei-Wu Chao, Jay F. Kunze, Weimin Dai, Sudarshan K. Loyalka
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 261-270
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34927
Empirical Model Development and Validation with Dynamic Learning in the Recurrent Multilayer Perceptron
Alexander G. Parlos, Kil T. Chong, Amir F. Atiya
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 271-290
Technical Paper | Reactor Control | doi.org/10.13182/NT94-A34928
Evaluation of the Reactivity Expansion Defect for Small Solid-Core Reactors and Components
Salim Jahshan, Samim Anghaie
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 291-292
Technical Note | Fission Reactor | doi.org/10.13182/NT94-A34929
Thermal Performance Test of a Coaxial Double-Tube Hot-Gas Duct
Ikuo Ioka, Yoshiyuki Inagaki, Kazuhiko Kunitomi, Yoshiaki Miyamoto, Kunihiko Suzuki
Nuclear Technology | Volume 105 | Number 2 | February 1994 | Pages 293-299
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34930
Secondary-Side Feed-and-Bleed Effectiveness in Pressurized Water Reactors
Alessandro Annunziato
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 301-321
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34932
Use of Post-Chernobyl Data from Norway to Validate the Long-Term Exposure Pathway Models in the Accident Consequence Code MACCS
Ulf Tveten
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 322-333
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34933
The Composition of Aerosols Generated During a Severe Reactor Accident: Experimental Results from the Power Burst Facility Severe Fuel Damage Test 1-4
David A. Petti, Richard R. Hobbins, Donald L. Hagrman
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 334-345
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34934
Fabrication of (Pu0.55U0 .45)C Fuel Pellets for the Second Core of the Fast Breeder Test Reactor in India
Chaitanyamoy Ganguly, Parameshwar Venkappa Hegde, Gyan Chand Jain
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 346-354
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A34935
Prototype Oxide Breeder Tests in the Fast Flux Test Facility
Allen L. Pitner, Brent C. Gneiting, Ronald B. Baker, Samuel L. Hecht
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 355-365
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A34936
Fission Product Release from Uranium-Aluminum Alloy Fuel in SLOWPOKE-2 Reactors
Brent J. Lewis, Anne C. Harnden-Gillis, Leslie G. I. Bennett
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 366-380
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A34937
Modeling of Transient Thermal-Hydraulic Phenomena in a Once-Through Steam Generator During Auxiliary Feedwater Injection
B. K. Kamboj, S. M. Ghiaasiaan, S. I. AbdeL-Khalik
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 381-394
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34938
An Analytical Model of the Swirl Vane Steam Separator for Boiling Water Reactors
Curt M. Betts, Mark R. Galvin, Janet R. Green,† V. Melvin Guymon, Stephen M. Slater,‡, Andrew C. Klein
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 395-410
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34939
Thermal-Hydraulic Analysis of the Advanced Neutron Source Reactor Refueling Process
Yousri Elkassabgi, Graydon L. Yoder, Wallace R. Gambill
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 411-420
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34940
Effective Thermal Conductivity and Edge Conductance Model for a Spent-Fuel Assembly
Randall D. Manteufel, Neil E. Todreas
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 421-440
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34941
Elements of a Radioactive Waste Management Course
Audeen W. Fentiman
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 441-446
Technical Paper | Education | doi.org/10.13182/NT94-A34942
Self-Initialization Algorithm of the Kuosheng Plant Analyzer
Shih-Jen Wang, Chun-Sheng Chien, Suh-Chyn Jeng
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 447-456
Technical Paper | Radiation Protection | doi.org/10.13182/NT94-A34943
Congo Red/Polyvinyl Alcohol Film Dosimeter for Gamma Rays and Electrons
Woon Hyuk Chung
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 457-458
Technical Note | Radiation Protection | doi.org/10.13182/NT94-A34944
