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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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Nuclear Technology
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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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Integrated Information System for Analysis of Nuclear Power Plants
Alex Galperin, Kurt Hofer
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 1-12
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A35038
Critical and Power Experiments on the Low-Enriched Uranium Core of the Upgraded Pakistan Research Reactor-1
Saleem A. Ansari, Masood Iqbal, Liaqat Ali, N. M. Butt
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 13-23
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A35039
Core Design of a Direct-Cycle, Supercritical-Water-Cooled Fast Breeder Reactor
Tatjana Jevremovic, Yoshiaki Oka, Sei-Ichi Koshizuka
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 24-32
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A35040
The HEVA Experimental Program
Jean-Pierre Leveque, Bernard Andre, Gérard Ducros, Gilles Le Marois, Gilbert Lhiaubet
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 33-44
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A35041
Boiling Water Reactor Fuel Behavior at Burnup of 26 GWd/tonne U Under Reactivity-Initiated Accident Conditions
Takehiko Nakamura, Makio Yoshinaga, Makoto Sobajima, Kiyomi Ishijima, Toshio Fujishiro
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 45-60
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A35042
Equilibrium Cycle Calculations for Transuranics Recycling in Pressurized Water Reactors
John C. Lee, Jie Du
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 61-79
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A35043
Near-Field Diffusion Releases Through One and Two Finite Planar Zones from a Nuclear Waste Package
Tzou-Shin Ueng, William J. O’Connell
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 80-89
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT94-A35044
Treatability Testing to Evaluate What Can Work
Dirk Gombert II
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 90-99
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT94-A35045
Factors Influencing the Precoat Filtration of Boiling Water Reactor Water Streams
Hans-Peter Hermansson, Göran Persson, Anneli Reinvall
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 100-111
Technical Paper | Material | doi.org/10.13182/NT94-A35046
Two-Dimensional Steady-State and Transient Analyses of Single-Cell Thermionic Fuel Elements
Mohamed S. El-Genk, Huimin Xue
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 112-125
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A35047
Mass Optimization Studies of Gamma Shield Materials for Space Nuclear Reactors
Vojislav Banjac, A. Sharif Heger
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 126-136
Technical Paper | Radiation Protection | doi.org/10.13182/NT94-A35048
Qualification of the ARROTTA Code for Light Water Reactor Accident Analysis
Ping-Hue Huang, Jing-Tong Yang, Jen-Ying Wu
Nuclear Technology | Volume 108 | Number 1 | October 1994 | Pages 137-150
Technical Note | Nuclear Reactor Safety | doi.org/10.13182/NT94-A35049
Conceptual Designs of Epithermal Neutron Beams for Boron Neutron Capture Therapy from Low-Power Reactors
Hungyuan B. Liu, Robert M. Brugger
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 151-156
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A35026
Development and Comparison of a TOPAZ-II System Model with Experimental Data
Dmitry V. Paramonov, Mohamed S. El-Genk
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 157-170
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A35027
An Integrated Model of the TOPAZ-II Electromagnetic Pump
Mohamed S. El-Genk, Dmitry V. Paramonov
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 171-180
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A35028
Characteristics of the Flow-Controlled Accumulator
Tadashi Shiraishi, Hisato Watakabe, Nobuo Nakamori, Kozo Tabuchi, Yoji Takayama, Takayoshi Sugizaki
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 181-190
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A35029
RELAP5/MOD3 Simulation of the Loss of the Residual Heat Removal System During a Midloop Operation Experiment Conducted at the ROSA-IV Large-Scale Test Facility
Yassin A. Hassan, Sibashis S. Banerjee
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 191-206
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A35030
Strength of Silicon Carbide Layers of Fuel Particles for High-Temperature Gas-Cooled Reactors
Paul A. Lessing, Ronald J. Heaps
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 207-234
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A35031
Preliminary Neutronics Investigation of the Delayed Neutron Nondestructive Assay of an Integral Fast Reactor Waste Canister
Cheng-Wei Wu, Douglass L. Henderson, Edgar F. Bennett
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 235-255
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A35032
A Modeling Study of Parameters ControIIing Local Concentration Processes in Pressurized Water Reactor Steam Generators
Peter J. Millett, James M. Fenton
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 256-265
Technical Paper | Material | doi.org/10.13182/NT94-A35033
Effect of External Cooling on the Thermal Behavior of a Boiling Water Reactor Vessel Lower Head
Hyunjae Park, V. K. Dhir, William E. Kastenberg
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 266-282
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A35034
Error Prediction for a Nuclear Power Plant Fault-Diagnostic Advisor Using Neural Networks
Keehoon Kim, Eric B. Bartlett
Nuclear Technology | Volume 108 | Number 2 | November 1994 | Pages 283-297
Technical Paper | Reactor Control | doi.org/10.13182/NT94-A35035
Cross-Section Parameterization Using Irradiation Time and Exposure for Global Depletion Analysis
Steven E. Aumeier, John C. Lee, Derek M. Cribley, William R. Martin
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 299-319
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A35014
Rough Estimates of Severe Accident Containment Loads Accompanying Vessel Breach in Boiling Water Reactors
Mark T. Leonard
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 320-337
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A35015
Analysis of a Core Disruptive Accident in a Liquid-Metal-Cooled Fast Breeder Reactor Using the Near-Characteristic Method
Jayan K. George, Jagdeep B. Doshi
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 338-349
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A35016
Stability Measurements in the German Nuclear Power Plant Wuergassen During Cycle 14
Ethwart Pollmann, Joachim Schulze, Dieter Kreuter
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 350-360
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A35017
Chinese Experience in the Removal of Actinides from Highly Active Waste by Trialkylphosphine-Oxide Extraction
Yongjun Zhu, Rongzhou Jiao
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 361-369
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT94-A35018
Development of a Demister for a Waste Evaporator Using a Hydrophobic Membrane Filter
Kiyomi Funabashi, Koichi Chino, Tsutomu Baba, Hiroyuki Tsuchiya, Tatsuo Izumida, Toshio Sawa
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 370-378
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT94-A35019
The Benchmarking of a Homogeneous Equilibrium Model for Analysis of Spent-Fuel Shipping Containers
Steven J. Manson, Dale E. Klein
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 379-386
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT94-A35020
RELAP5/MOD3 Modeling of Water Column Rejoining and a Water Slug Propelled by Noncondensable Gas
W. S. Yeung, J. Shirkov, F. Seifaee
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 387-394
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A35021
Validation of the ATR-SINDA Fuel Plate Model Using Advanced Test Reactor Startup Data
Steven T. Polkinghorne
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 395-412
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A35022
A Transient Analysis of Decomposition and Erosion of Concrete Exposed to a Surface Heat Flux
Arif Nesimi Kiliç
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 413-420
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A35023
Maximum Likelihood Factor Analysis of the Reactor Coolant Pump System
William S. Grenzebach, Carolyn D. Heising, Thomas J. Marx
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 421-433
Technical Paper | Reactor Operation | doi.org/10.13182/NT94-A35024
