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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
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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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Systems Design of Direct-Cycle Supercritical-Water-Cooled Fast Reactors
Yoshiaki Oka, Sei-Ichi Koshizuka, Tatjana Jevremovic, Yasushi Okano
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 1-10
Technical Paper | Fission Reactor | doi.org/10.13182/NT95-A35064
Analysis of Epithermal Neutron Beam Experiments at the Hifar Reactor
Baiba V. Harrington, Geoffrey Constantine
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 11-20
Technical Paper | Fission Reactor | doi.org/10.13182/NT95-A35065
Outline of the Uncertainty Methodology Based on Accuracy Extrapolation
Francesco D’auria, Nenad Debrecin, Giorgio Maria Galassi
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 21-38
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT109-21
Modeling of Cesium Release from Light Water Reactor Fuel Under Severe Accident Conditions
Anne C. Harnden-Gillis, Brent J. Lewis, William S. Andrews, Peter L. Purdy, Morris F. Osborne, Richard A. Lorenz
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 39-53
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35067
Evaluation of the Uncertainties in the Source Distribution for Pressure Vessel Neutron Fluence Calculations
Alireza Haghighat, Moussa Mahgerefteh, Bojan G. Petrovic
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 54-75
Technical Paper | Material | doi.org/10.13182/NT95-A35068
A Fluid Discontinuity Tracking Methodology for Finite Difference Thermal-Hydraulic Simulation
Michael J. Zavisca, J. Michael Doster
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 76-86
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35069
Neutronics and Thermal-Hydraulics Analyses of the Pellet Bed Reactor for Nuclear Thermal Propulsion
Nicholas J. Morley, Mohamed S. El-Genk
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 87-107
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35070
Numerical Predictions of Turbulent Flow Around a Structure Via the k-∈ Model for Reactor Vessel Auxiliary Cooling System Performance Analysis
Constantine P. Tzanos
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 108-122
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35071
Helium-Air Exchange Flow Through Annular and Round Tubes
Motoo Fumizawa, Makoto Hishida
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 123-131
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35072
Determination of Time-Dependent Void Fraction Distribution in Bubbly Two-Phase Flow by A Real-Time Neutron Radiography Technique
G. D. Harvel, J. S. Chang, V. Santhana Krishnan
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 132-141
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35073
Simplified Evaluation Models for Total Fission Number in a Criticality Accident
Yasushi Nomura, Hiroshi Okuno
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 142-152
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT95-A35074
Feedwater Control System Design with the Kuosheng Plant Analyzer
Shih-Jen Wang, Shih-Hsiin Chang, Chun-Sheng Chien, Ling-Yao Chou
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 153-160
Technical Paper | Reactor Control | doi.org/10.13182/NT95-A35075
Simple Method for Technetium Removal from Aqueous Solutions
G. D. Del Cul, William D. Bostick
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 161-162
Technical Note | Material | doi.org/10.13182/NT95-A35076
Modeling of Molten Metal/Water Interactions
Ali Uludogan, Michael L. Corradini
Nuclear Technology | Volume 109 | Number 2 | February 1995 | Pages 171-186
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT109-171
Influence of Isolation Condensers on Boiling Water Reactor Performance During an Anticipated Transient Without Scram
Hasna J. Khan, Hsiang-Shou Cheng, Upendra S. Rohatgi
Nuclear Technology | Volume 109 | Number 2 | February 1995 | Pages 187-206
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35052
Iodine Release During a Steam Generator Tube Rupture
James P. Adams
Nuclear Technology | Volume 109 | Number 2 | February 1995 | Pages 207-215
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35053
Extraction Chromatographic Separation of Minor Actinides from PUREX High-Level Wastes Using CMPO
J. N. Mathur, M. S. Murali, R. H. Iyer, A. Ramanujam, P. S. Dhami, V. Gopalakrishnan, M. K. Rao, L. P. Badheka, Asoke Banerji
Nuclear Technology | Volume 109 | Number 2 | February 1995 | Pages 216-225
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT95-A35054
Reactor-Based Prompt Gamma Neutron Activation Setup Using a Low-Power Research Reactor
Chien Chung, Liq-Ji Yuan
Nuclear Technology | Volume 109 | Number 2 | February 1995 | Pages 226-235
Technical Paper | Radiation Application | doi.org/10.13182/NT95-A35055
Experimental Study on Flow Rate Measurement of Buoyancy-Driven Exchange Flow
Motoo Fumizawa
Nuclear Technology | Volume 109 | Number 2 | February 1995 | Pages 236-245
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35056
Fundamental Study on Duplex Steam Generator Tubes for Liquid-Metal-Cooled Fast Reactors
Masanori Aritomi, Tomoaki Mizushima, Hiroshi Yabuta
Nuclear Technology | Volume 109 | Number 2 | February 1995 | Pages 246-254
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35057
Intelligent Alarm-Processing System for Nuclear Power Plants
Norio Naito, Shiroh Ohtsuka
Nuclear Technology | Volume 109 | Number 2 | February 1995 | Pages 255-264
Technical Paper | Reactor Operation | doi.org/10.13182/NT95-A35058
In Situ Gamma Spectrometry of Piping in a CANDU Heat Transport System — Application During Decontamination
Aamir Husain, Calvin E. Breckenridge, David Storey
Nuclear Technology | Volume 109 | Number 2 | February 1995 | Pages 265-274
Technical Paper | Reactor Operation | doi.org/10.13182/NT95-A35059
Simulation of a Marine Nuclear Reactor
Tsuyoshi Kusunoki, Masahiko Kyouya, Hideo Kobayashi, Masa-Aki Ochiai
Nuclear Technology | Volume 109 | Number 2 | February 1995 | Pages 275-285
Technical Paper | Reactor Operation | doi.org/10.13182/NT95-A35060
Artificial Neural Networks Versus Conventional Methods for Boiling Water Reactor Stability Monitoring
Tim H. J. J. van der Hagen
Nuclear Technology | Volume 109 | Number 2 | February 1995 | Pages 286-305
Technical Paper | Reactor Control | doi.org/10.13182/NT95-A35061
Design Study of Lead- and Lead-Bismuth-Cooled Small Long-Life Nuclear Power Reactors Using Metallic and Nitride Fuel
Hiroshi Sekimoto, Zaki Su’ud
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 307-313
Technical Paper | Fission Reactor | doi.org/10.13182/NT109-307
Design of Neutron Beams for Neutron Capture Therapy Using a 300-kW Slab TRIGA Reactor
Hungyuan B. Liu
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 314-326
Technical Paper | Fission Reactor | doi.org/10.13182/NT95-A35080
Simulation of the IAEA’s Fourth Standard Problem Exercise Small-Break Loss-of-Coolant Accident Using RELAP5/MOD3.1
Peter P. Cebull, Yassin A. Hassan
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 327-337
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35081
Passive Safety Injection Experiments with a Large-Scale Pressurized Water Reactor Simulator
Taisuke Yonomoto, Yutaka Kukita, Yoshinari Anoda, Hideaki Asaka
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 338-345
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35082
Implementation of a New Model for Gravitational Collision Cross Sections in Nuclear Aerosol Codes
Robert L. Buckley, Sudarshan K. Loyalka
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 346-356
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35083
Nuclear Analysis for the Boraflex Used in a Typical Spent-Fuel Storage Assembly
Insoo Jun, Myung Jae Song
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 357-365
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35084
Investigation of Silver-Impregnated Alumina for Removal of Radioactive Methyl Iodide
Kiyomi Funabashi, Tetsuo Fukasawa, Makoto Kikuchi
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 366-372
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT95-A35085
Remodeling of the Oxidant Species During Radiolysis of High-Temperature Water in a Pressurized Water Reactor
Hilbert Christensen
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 373-382
Technical Paper | Material | doi.org/10.13182/NT95-A35086
Calculation and Benchmarking of an Azimuthal Pressure Vessel Neutron Fluence Distribution Using the Boxer Code and Scraping Experiments
Frank Holzgrewe, Ferenc Hegedues, Jean M. Paratte
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 383-397
Technical Paper | Material | doi.org/10.13182/NT95-A35087
Investigation of Scale-Up Capability of RELAP5/MOD3 and Scaling Distortion in the IIST Facility Via Natural Circulation Experiments
Yuh-Ming Ferng, Bau-Shei Pei, Tuan-Ji Ding
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 398-411
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35088
Operational Control of Boiling Water Reactor Stability
Christofer M. Mowry, Israel Nir
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 412-428
Technical Paper | Reactor Control | doi.org/10.13182/NT95-A35089
Assessment of Costs and Benefits Associated with Resolution of Generic Safety Issue 143—Availability of Heating, Ventilation, and Air Conditioning and Chilled Water Systems
Philip M. Daling, Jay E. Marler, Truong V. Vo, Hanh K. Phan, John R. Friley
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 429-436
Technical Note | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35090
