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Division Spotlight
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.
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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A Rule-Based Expert System for Automatic Control Rod Pattern Generation for Boiling Water Reactors
Lian Shin Lin, Chaung Lin
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 1-8
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34563
In-Core Nuclear Fuel Management Optimization for Pressurized Water Reactors Utilizing Simulated Annealing
David J. Kropaczek, Paul J. Turinsky
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 9-32
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT95-1-9
Prediction of Mass Transfer and Heat Evolution of Purex Pulsed Columns by the DYNAC Computer Model
Masahiro Nabeshima
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 33-43
Technical Paper | Enrichment and Reprocessing | doi.org/10.13182/NT91-A34565
Advanced Remote Decontamination Techniques Reduce Costs and Radiation Doses
Y. Bruce Katayama, Langdon K. Holton, Jr., Galen N. Buck, James F. Hutchens, Mark S. Culverhouse
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 44-53
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT91-A34566
Preliminary Assessments for Disposal of High-Level Waste Within Small Islets
Fu-Long Chen, Shih-Hai Li, Ge-Ping Yu
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 54-63
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT91-A34567
A DSNP Movable Boundary U-Tube Steam Generator Model
Doron Gal, David Saphier, Ezra Elias
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 64-76
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34568
Two-Phase Flow Interfacial Drag for Once-Through Steam Generators
Yassin A. Hassan, Omar Rais
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 77-86
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34569
Verification of Using a Single Void Fraction Sensor to Identify Two-Phase Flow Patterns
Y. W. Wang, B. S. Pei, W. K. Lin
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 87-94
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34570
Determining Wall Superheat Under Fully Developed Nucleate Boiling in Plate-Type Research Reactor Cores with Low-Velocity Upward Flows
Mohamed Belhadj, Tunc Aldemir, Richard N. Christensen
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 95-102
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34571
Application of Mixture Drift Flux Equations to Vertical Separating Flows
Kyungdoo Kim, J. Michael Doster
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 103-115
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34572
Designing a Knowledge-Based Operator Support System for Practical Applications
Yushi Fujita, Makoto Tohyama, Ichiro Yanagisawa, Toshio Ida, Hiroshi Arikawa
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 116-128
Technical Paper | Reactor Operation | doi.org/10.13182/NT91-A34573
Sensitivity and Uncertainty Analysis of Integral Physics Parameters in High-Conversion Reactor Systems
John R. White, Thomas F. DeLorey
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 129-147
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34551
Corrosion Product Radionuclide Buildup in Fast Flux Test Facility Heat Transport System Cells
William F. Brehm, Robert L. Simons
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 148-155
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34552
Xenon Dynamics and Related Parameters in the Taiwan Research Reactor
Shih-Jen Wang, Ming-Song Lin
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 156-161
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34553
Effect of Flushing Boron During a Boiling Water Reactor Anticipated Transient Without Scram
Dragan Mirkovic, David J. Diamond
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 162-174
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34554
Theory and Verification of a Fuel Rod Mechanics Model Based on a Two-Dimensional Finite Element Method with Consideration of Fuel/Cladding Contact and Friction
Klaus L. Nissen
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 175-192
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34555
A Simple Nondestructive Measurement System for Spent-Fuel Management
Hermann Würz
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 193-206
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34556
Analysis of Cylindrical and Annular Pulsed Columns with Different Internal Plates in the Purex Process
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 207-218
Technical Paper | Environment and Reprocessing System | doi.org/10.13182/NT91-A34557
Elaborated Constitutive Equations for Structural Analysis for Creep, Swelling, and Damage Under Irradiation
S. Murakami, M. Mizuno
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 219-227
Technical Paper | Material | doi.org/10.13182/NT91-A34558
Thermal-Hydraulic Systems Safety Analysis to Support the Design Process for the Advanced Neutron Source Reactor
C. D. Fletcher, L. S. Ghan
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 228-246
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34559
The Probability Density Function of the Total Departure from Nucleate Boiling Ratio
Ross C. Anderson
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 247-250
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34560
Analysis of DRACS and DRACS-RVACS Decay Heat Removal Experiments
Constantine P. Tzanos, Dean R. Pedersen
Nuclear Technology | Volume 95 | Number 3 | September 1991 | Pages 253-265
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34575
An Alarm Processing System for a Nuclear Power Plant Using Artificial Intelligence Techniques
Joon On Yang, Soon Heung Chang
Nuclear Technology | Volume 95 | Number 3 | September 1991 | Pages 266-271
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34576
Monte Carlo Methods, Models, and Applications to the Advanced Neutron Source
Everett L. Redmond II, John M. Ryskamp
Nuclear Technology | Volume 95 | Number 3 | September 1991 | Pages 272-286
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34577
Review of Experimental Results on Light Water Reactor Core Melt Progression
Richard R. Hobbins, David A. Petti, Daniel J. Osetek, Donald L. Hagrman
Nuclear Technology | Volume 95 | Number 3 | September 1991 | Pages 287-307
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34578
Probabilistic Safety Assessment of Support Systems for CANDU Stations
Hymie S. Shapiro
Nuclear Technology | Volume 95 | Number 3 | September 1991 | Pages 308-313
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT91-A34579
A Comprehensive Fission Gas Release Model Considering Multiple Bubble Sizes on the Grain Boundary Under Steady-State Conditions
Woan Hwang, Ho Chun Suk, Won Mok Jae
Nuclear Technology | Volume 95 | Number 3 | September 1991 | Pages 314-324
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34580
Safety Demonstration Tests of Hypothetical Explosive Burning in the Cell and Air Ventilation System in a Nuclear Fuel Reprocessing Plant
Gunji Nisio, Motoe Suzuki, Shigeo Mukaide, Junichi Takada, Michio Tsukamoto, Tadao Koike
Nuclear Technology | Volume 95 | Number 3 | September 1991 | Pages 325-336
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT91-A34581
Design of a Neutron Gauge for the Detection and Measurement of Water Ingression in Flat Roofs
Hugues W. Bonin, Christopher J. Thorp
Nuclear Technology | Volume 95 | Number 3 | September 1991 | Pages 337-348
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT91-A34582
Development of a Parallelism Analysis Integrated System for a Fast-Running Pressurized Water Reactor Plant Predictive Simulator
Kazunori Sasaki, Hiroo Kanamaru, Mitsuo Tanaka
Nuclear Technology | Volume 95 | Number 3 | September 1991 | Pages 349-365
Technical Paper | Reactor Operation | doi.org/10.13182/NT91-A34583
The Buildup of Confined Pressure at Salts in Decaying Radioactive Waste
K. H. G. Ashbee
Nuclear Technology | Volume 95 | Number 3 | September 1991 | Pages 366-371
Technical Note | Radioactive Waste Management | doi.org/10.13182/NT91-A34584
