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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
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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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Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
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Considerations for Realistic Emergency Core Cooling System Evaluation Methodology for Light Water Reactors
U. S. Rohatgi, Pradip Saha, V. K. Chexal
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 11-26
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33893
An On-Line Pressurizer Surveillance System Design to Prevent Small-Break Loss-of-Coolant Accidents Through Power-Operated Relief Valves Using a Microcomputer
Jong Ho Lee, Soon Heung Chang
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 27-40
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33894
Determination of Appendix K Conservatisms for Westinghouse Pressurized Water Reactors Using TRAC-PD2/MOD1
U. S. Rohatgi, Christine Yuelys-Miksis, Pradip Saha
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 41-50
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33895
X-Ray Photoelectron Spectroscopy and Electron Probe X-Ray Microanalysis Investigation and Chemical Speciation of Aerosol Samples Formed in Light Water Reactor Core-Melting Experiments
Harald Moers, Hanns Klewe-Nebenius, Hans J. Ache
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 51-59
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33896
The Applications of Nuclear Technology in Reactor Siting
Pao-Shan Weng, Hseuh-Hsing Cheng, Chuan-Chung Hsu, Kuan-Han Sun
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 60-67
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33897
In-Core Fuel Cycle Transients
Jeffery David Lewins
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 68-83
Technical Paper | Fuel Cycle | doi.org/10.13182/NT87-A33898
The Leaching Behavior of a Glass Waste Form—Part III: The Mathematical Leaching Model
Tsunetaka Banba, Takashi Murakami, Hideo Kimura
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 84-90
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A33899
RETRAN Overview
Lance J. Agee
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 91-97
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33900
RETRAN Generic Review—A Retrospection
Thomas L. Temple
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 98-104
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33901
The Development and Application of System Analysis at Kansas Gas and Electric Company
Terry J. Garrett, Steven W. Sorrell
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 105-112
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33902
Reducing Scram Frequency by Modifying Reactor Setpoints for a Westinghouse Four-Loop Plant
Jason Chao, William H. Layman, Gary Vine
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 113-125
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33903
Nodalization Study of the Westinghouse Model E Steam Generator Secondary Side
Robert O. Montgomery, Kenneth L. Peddicord, Roger L. Boyer, Charles R. Albury
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 126-136
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33904
RETRAN Modeling of the Westinghouse Model D Steam Generator
Lance G. Riniker, Kevin B. Ramsden
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 137-142
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33905
RETRAN Analysis of Susquehanna Steam Electric Station Unit 2 Moisture Separator Drain Tank Level Transient Response
Laurence M. Olson
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 143-165
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33906
A Comparison of RETRAN-02 and TRAC-PF1 Simulations of a Loss of Off-Site Power Cooldown to Residual Heat Removal Entry Conditions at Calvert Cliffs Nuclear Power Plant
Trevor L. Cook, Steven M. Mirsky
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 166-171
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33907
Safety Analyses Using RETRAN-02 with Relaxed Trip Setpoints on Combustion Engineering Reactors
Bruce Ching, Chong Chiu, Jason Chao, William H. Layman, Gary Vine
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 172-184
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33908
Passive Emergency Cooling Systems for Boiling Water Reactors (PECOS-BWR)
Charles W. Forsberg
Nuclear Technology | Volume 76 | Number 1 | January 1987 | Pages 185-192
Technical Note | Fission Reactor | doi.org/10.13182/NT87-A33909
Determination of Isotopic Ratios from Fuel Burnup
John C. Lee, Sin Tao Hsue
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 203-208
Technical Paper | Fuel Cycle | doi.org/10.13182/NT87-A33874
ELOCA-A: A Code for Radial and Axial Behavior of CANDU Fuel Elements at High Temperatures
Mukesh Tayal, Ed Mischkot, Harve E. Sills, A. W. L. Segel
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 209-220
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT87-A33875
Properties of Bentonite Clay as Buffer Material in High-Level Waste Geological Disposal. Part I: Chemical Species Contained in Bentonite
Masanori Takahashi, Masayuki Muroi, Atsuyuki Inoue, Masahiro Aoki, Makoto Takizawa, Kenkichi Ishigure, Norihiko Fujita
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 221-228
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT87-A33876
An Experimental Correlation of Cross-Flow Pressure Drop for Triangular Array Wire-Wrapped Rod Assemblies
Kune Yull Suh, Neil E. Todreas
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 229-240
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33877
In Vivo Measurement of Organ Mercury by Prompt Gamma Activation Analysis Using a Mobile Nuclear Reactor
Pao-Shu Chang, Yau-Hui ho, Chien Chung, Liq-Ji Yuan, Pao-Shan Weng
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 241-247
Technical Paper | Analyse | doi.org/10.13182/NT87-A33878
Simulation of the Transient Response of Ionization Chambers to Bias Voltage Perturbations
Tunc Aldemir, Steven A. Arndt, Don. W. Miller
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 248-259
Technical Paper | Technique | doi.org/10.13182/NT87-A33879
The Formation of Surface Layers and Reaction Products in the Leaching of Defense Borosilicate Nuclear Waste Glass
Alan B. Harker, John F. Flintoff
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 263-275
Performance of Borosilicate Glass High-Level Waste Forms in Disposal Systems | Radioactive Waste Management | doi.org/10.13182/NT87-A33880
A Guillotine Tube Rupture Modeling Technique Using RETRAN-02
Peter J. Jensen, James F. Lang, Jason Chao
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 279-289
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33881
A Parametric Study of an Anticipated Transient Without Scram in a Westinghouse Four-Loop Plant
Peter J. Jensen, Kent D. Richert, Jason Chao
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 290-302
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33882
Moderator Feedback Effects in Two-Dimensional Nodal Methods for Pressurized Water Reactor Analysis
Thomas J. Downar
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 303-307
Technical Note | Fission Reactor | doi.org/10.13182/NT87-A33883
Finite Element Analysis of Boiling Water Reactor Fuel Channel Bulge and Bow
David P. Chan, David L. Larkin
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 319-324
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33917
An Analysis of Initiating and Transition Phases for an Unprotected Loss-of-Flow Accident in an Axially Heterogeneous Fast Breeder Reactor Core
Kazuo Azekura, Kikuo Umegaki, Kotaro Inoue, Sang K. Rhow, James E. McElroy, Dennis M. Switick
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 325-336
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33918
Liquid-Metal Fast Breeder Reactor Intermediate Heat Exchanger Transient Modeling for Faster Than Real-Time Analysis
Constantine P. Tzanos
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 337-351
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33919
Development of a Postscram Analyzer for Boiling Water Reactors
Bill K.-H. Sun, Robert Colley, David G. Cain, John W. Hallam
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 352-359
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33920
Experimental Studies of the Air Coolability of TRIGA Reactors Following a Loss-of-Coolant Accident
Mohamed S. El-Genk, Sung-Ho Kim, Galal M. Zaki, Jeffrey S. Philbin, James F. Schulze, Fabian C. Foushée
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 360-369
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33921
A Probabilistic Analysis Method to Evaluate the Effect of Human Factors on Plant Safety
Hiroshi Ujita
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 370-376
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33922
A Comparison of Measured Radionuclide Release Rates from Three Mile Island Unit-2 Core Debris for Different Oxygen Chemical Potentials
V. F. Baston, K. J. Hofstetter, Robert F. Ryan
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 377-389
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33923
CANDU Pressurized Heavy Water Reactor Thorium-233U Oxide Fuel Evaluation Based on Optimal Fuel Management
Hugues W. Bonin
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 390-399
Technical Paper | Fuel Cycle | doi.org/10.13182/NT87-A33924
Gamma Radiation Effects on Time-Dependent Iodine Partitioning
Paul W. Marshall, Jeffrey B. Lutz, James L. Kelly
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 400-407
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A33925
Radiography Experiments at Argonne National Laboratory
Wade J. Richards, Howard A. Larson
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 408-419
Technical Paper | Material | doi.org/10.13182/NT87-A33926
Total Control Worth by Inspection
Charles R. Marotta
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 420-422
Technical Note | Fission Reactor | doi.org/10.13182/NT87-A33927
