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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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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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Development of Mixed-Oxide Fuel Manufacture in the United Kingdom and the Influence of Fuel Characteristics on Irradiation Performance
Hugh M. MacLeod, Geoffrey Yates
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 3-17
Technical Paper | Mixed-Oxide Fuel / Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34798
Plutonium Processing at the Siemens Hanau Fuel Fabrication Plant
Jürgen Krellmann
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 18-28
Technical Paper | Mixed-Oxide Fuel / Enrichment and Reprocessing System | doi.org/10.13182/NT93-A34799
Irradiation Behavior of UO2/PuO2 Fuel in Light Water Reactors
Wolfgang Goll, Hans-Peter Fuchs, Reiner Manzel, Fritz U. Schlemmer
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 29-46
Technical Paper | Mixed-Oxide Fuel / Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34800
In-Pile Performance of Mixed-Oxide Fuel with Particular Emphasis on MIMAS Fuel
P. Deramaix, D. Haas, J. Van De Velde
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 47-53
Technical Paper | Mixed-Oxide Fuel / Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34801
Experience in PWR and BWR Mixed-Oxide Fuel Management
Gerhard J. Schlosser, Wolf-Dieter Krebs, Peter Urban
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 54-67
Technical Paper | Mixed-Oxide Fuel / Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34802
Investigation of the Nuclear Inventories of High-Exposure PWR Mixed-Oxide Fuels with Multiple Recycling of Self-Generated Plutonium
Hans-Werner Wiese
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 68-80
Technical Paper | Mixed-Oxide Fuel / Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34803
Validation of Fuel Bundle Mechanical Performance Code ÉTOILE with Bundle/Duct Interaction Experimental Data
Masatoshi Nakagawa
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 81-89
Technical Paper | Mixed-Oxide Fuel / Fission Reactor | doi.org/10.13182/NT93-A34804
Development of a Connectivity Verification System for Sequence Diagrams of Power Plants
Mitsuko Fukuda, Naoyuki Yamada, Ken’ichi Kan, Mitsugu Utsunomiya
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 90-99
Technical Paper | Mixed-Oxide Fuel / Fission Reactor | doi.org/10.13182/NT93-A34805
Global Analysis of Bundle Behavior in Pressurized Water Reactor Specific CORA Experiments
Wolfgang Hering, Kazuo Minato, Fumihisa Nagase
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 100-115
Technical Paper | Mixed-Oxide Fuel / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34806
RELAP5/MOD2 Split Reactor Vessel Model and Steamline Break Analysis
Stojan Petelin, Borut Mavko, Oton Gortnar
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 116-124
Technical Paper | Mixed-Oxide Fuel / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34807
Ex-Core Detector Response Caused by Control Rod Misalignment Observed During Operation of the Reactor on the Nuclear Ship Mutsu
Masafumi Itagaki, Yoshinori Miyoshi, Kazuhiko Gakuhari, Noboru Okada, Tomohiro Sakai
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 125-136
Technical Paper | Mixed-Oxide Fuel / Reactor Operation | doi.org/10.13182/NT93-A34808
Formalisms for Handling Phenomenological Uncertainties: The Concepts of Probability, Frequency, Variability, and Probability of Frequency
Stan Kaplan
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 137-142
Technical Note | Mixed-Oxide Fuel / Nuclear Reactor Safety | doi.org/10.13182/NT93-A34809
Transient and Load-Following Characteristics of a Fully Integrated Single-Cell Thermionic Fuel Element
Mohamed S. El-Genk, Huimin Xue, Chris Murray
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 145-166
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34813
Proof of Principle of a Nuclear Turbine Flowmeter
Tim H. J. J. Van Der Hagen
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 167-176
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A34814
Application of Neural Networks to a Connectionist Expert System for Transient Identification in Nuclear Power Plants
Se Woo Cheon, Soon Heung Chang
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 177-191
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34815
Reduction of the Reactivity of Water Ingress in Modular Pebble-Bed High-Temperature Reactors
E. Teuchert, K. A. Haas, H. J. Rütten, Yuliang Sun
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 192-195
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34816
Error Propagation for Gamma Spectroscopy and Neutron Coincidence Counting for Plutonium-Bearing Materials
Ming-Shih Lu, Theodor Teichmann
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 196-209
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34817
Evaluation of Fission Gas Release in High-Burnup Light Water Reactor Fuel Rods
John O. Barner, Mitchel E. Cunningham, Maxwell D. Freshley, Donald D. Lanning
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 210-231
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34818
Development of the FACE Computer Code to Evaluate the Safety of an Air Ventilation System During a Postulated Solvent Fire in a Nuclear Fuel Reprocessing Plant
Gunji Nishio, Noboru Yamazaki
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 232-251
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT93-A34819
The Effect of Correlated Flow in Pulsed Column Contactors Using the Purex Process
John F. Geldard, Adolph L. Beyerlein
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 252-258
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT93-A34820
Characterization of the Thermalness of a Fissile System with a Two-Group Diffusion Theory Parameter
Brent B. Bredehoft, Robert D. Busch
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 259-269
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT93-A34821
LRAD-Based Alpha-Particle Contamination Monitoring of Personnel and Equipment
Duncan W. MacArthur, Krag S. Allander, John A. Bounds, J. Lee McAtee
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 270-276
Technical Paper | Radiation Protection | doi.org/10.13182/NT93-A34822
Automatic Reactor Power Control for a Pressurized Water Reactor
Jung-In Choi, Yung-Joon Hah, Un-Chul Lee
Nuclear Technology | Volume 102 | Number 2 | May 1993 | Pages 277-286
Technical Paper | Reactor Operation | doi.org/10.13182/NT93-A34823
Development of an Automatic Metal Analysis System for Boiling Water Reactor Primary Water and Its Application
Hiroo Igarashi, Michio Nitto, Fumio Mizumiwa, Katumi Ohsumi
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 287-296
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A17027
Development of the Chinshan Plant Analyzer and Its Assessment with Plant Data
Shih-Jen Wang, Chun-Sheng Chien, Jung-Yuh Jang, Shaw-Cuang Lee
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 297-303
Technical Paper | Fission Reactor | doi.org/10.13182/NT93-A17028
Steam Generator Secondary pH During a Steam Generator Tube Rupture
James P. Adams, Eric S. Peterson
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 304-312
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A17029
Estimation of Burnup in Taiwan Research Reactor Fuel Pins by Using Nondestructive Techniques
Lung Kwang Pan, Cheng Si Tsao
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 313-322
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A17030
Radiochemical Evaluation for Debris-Induced Failures
G. Goncarovs
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 323-330
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A17031
Cadmium Transport Through Molten Salts in the Reprocessing of Spent Fuel for the Integral Fast Reactor
K. Michael Goff, Alfred Schneider, James E. Battles
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 331-340
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT93-A17032
New Separation Process for Neptunium, Plutonium, and Uranium Using Butyraldehydes as Reductants in Reprocessing
Gunzo Uchiyama, Sachio Fujine, Shinobu Hotoku, Mitsuru Maeda
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 341-352
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT93-A17033
A Liquid-Metal Reactor Core Demonstration Experiment Using HT-9
Alvia E. Bridges, Alan E. Waltar, Robert D. Leggett, Ronald B. Baker, Jerry L. Ethridge
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 353-366
Technical Paper | Material | doi.org/10.13182/NT93-A17034
Fracture and Tensile Properties of Irradiated Zircaloy-2 Pressure Tubes
Frank H. Huang, William J. Mills
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 367-375
Technical Paper | Material | doi.org/10.13182/NT93-A17035
Tensile Behavior of Neutron-Irradiated Martensitic Steels: A Review
R. L. Klueh
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 376-385
Technical Paper | Material | doi.org/10.13182/NT93-A17036
Local Heat Transfer Coefficients for Forced-Convection Condensation of Steam in a Vertical Tube in the Presence of a Noncondensable Gas
Mansoor Siddique, Michael W. Golay, Mujid S. Kazimi
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 386-402
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT93-A17037
Development of In-Service Inspection Plans for Nuclear Components at the Surry Unit 1 Nuclear Power Station
Truong V. Vo, Frederic A. Simonen, Steven R. Doctor, Brian W. Smith, Bryan F. Gore
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 403-415
Technical Paper | Reactor Operation | doi.org/10.13182/NT93-A17038
Modification to Unal’s Subcooled Flow Boiling Bubble Model
Richard A. Riemke
Nuclear Technology | Volume 102 | Number 3 | June 1993 | Pages 416-417
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT93-A17039
