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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
2024: The Year in Nuclear—April through June
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from April through May 2024.
Stay tuned for the top stories from the rest of the past year.
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Description of Critical Experiments in Spherical Geometry Containing UO2F2 Solution
Michelle Pitts, Farzad Rahnema, Tom G. Williamson, Fitz Trumble
Nuclear Technology | Volume 122 | Number 1 | April 1998 | Pages 1-18
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2847
Simulated AP600 Response to Small-Break Loss-of-Coolant-Accident and Non-Loss-of-Coolant-Accident Events: Analysis of SPES-2 Integral Test Results
M. T. Friend, R. F. Wright, R. Hundal, L. E. Hochreiter, M. Ogrins
Nuclear Technology | Volume 122 | Number 1 | April 1998 | Pages 19-42
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2848
Neutronic and Burnup Characteristics of an Actinide-Reduced Plutonium Fuel with Tungsten
Gray S. Chang
Nuclear Technology | Volume 122 | Number 1 | April 1998 | Pages 43-51
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT98-A2849
Comparison of Pressurized Water Reactor Core Characteristics for 100% Plutonium-Containing Loadings
Uwe Kasemeyer, Jean-Marie Paratte, Peter Grimm, Rakesh Chawla
Nuclear Technology | Volume 122 | Number 1 | April 1998 | Pages 52-63
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT98-A2850
Separation of Am(III) from Fission Product Lanthanides by Bis(2,4,4-Trimethylpentyl)-Dithiophosphinic Acid (HBTMPDTP) Extraction: Process Parameter Calculation
Jing Chen, Yongjun Zhu, Rongzhou Jiao
Nuclear Technology | Volume 122 | Number 1 | April 1998 | Pages 64-71
Technical Paper | Reprocessing | doi.org/10.13182/NT98-A2851
Radioactive Contamination Around a Boiling Water Reactor Main Turbine System and Procedures for Minimizing the Contaminated Area
Kei-Ichi Otoha, Shunsuke Uchida
Nuclear Technology | Volume 122 | Number 1 | April 1998 | Pages 72-82
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT98-A2852
A Water Level Controller for Steam Generators Estimating the Flow Errors and the Water Level Quantity Due to the Mass Capacity
Man Gyun Na
Nuclear Technology | Volume 122 | Number 1 | April 1998 | Pages 83-92
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT98-A2853
Simulation of Radionuclide Release from a Repository to the Biosphere: Using a Model-Coupling Concept
Björn Gylling, Luis Moreno, Ivars Neretnieks
Nuclear Technology | Volume 122 | Number 1 | April 1998 | Pages 93-103
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2854
Evaluation of Kalman Filters and Genetic Algorithms for Delayed-Neutron Nondestructive Assay Data Analyses
Steven E. Aumeier, J. Hope Forsmann
Nuclear Technology | Volume 122 | Number 1 | April 1998 | Pages 104-124
Technical Paper | Radioisotopes | doi.org/10.13182/NT98-A2855
RETRAN-03 Simulation of a Multiple Failure Event at Kori Unit 2
Kyungdoo Kim, Won-Pyo Chang, Kun-Joong Yoo, Seon-Hwa Lee, Chong-Bae Lee
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 125-131
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2856
The RETRAN-3D Code; Pressurized Water Reactor Multidimensional Neutron Kinetics Applications
Garry C. Gose, John G. Shatford, Lance J. Agee
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 132-145
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2857
RETRAN Benchmarks of LaSalle Units 1 and 2 Startup Tests
Eric T. Beaumont, Randall H. Jacobs
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 146-157
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2858
Analysis of WNP-2 Single-Loop Operation Using RETRAN-02
Shaw H. Bian, Dale E. Bush, Yat Yan Yung, Craig E. Peterson
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 158-169
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2859
A Probabilistic Approach for the Evaluation of Reactivity Insertion Accident Effects
Juan C. Ramos, Lance J. Agee, Antonio F. Dias
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 170-178
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2860
Design and Development of Fast Breeder Reactor Passive Reactivity Control Systems: LEM and LIM
Mitsuru Kambe, Masaki Uotani
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 179-195
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2861
Interaction Between Molecular Iodine in Gaseous Phase and a Coat of Paint - Influence of Temperature, Humidity, and Hydrothermal Treatment on Iodine Trapping Kinetics
A. Zoulalian, E. Belval-Haltier
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 196-210
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2862
Calculation of Radiation Dose Rates in a Water Layer in Contact with Used CANDU UO2 Fuel
Sham Sunder
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 211-221
Technical Paper | Radiation | doi.org/10.13182/NT98-A2863
Reduction of Neptunium(VI) by Butyraldehyde Isomers in Nitric Acid Solution
Gunzo Uchiyama, Shinobu Hotoku, Sachio Fujine, Mitsuru Maeda
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 222-227
Technical Paper | Enrichment | doi.org/10.13182/NT98-A2864
Ion-Exchange Considerations in Dilute Chemical Decontamination Processes Operated in the Regenerative Mode
Appadurai Lagorious Rufus, Sankaralingam Velmurugan, Padma Sasikumar, Valil Sreedharan Sathyaseelan, Sevilimedu Veeravalli Narasimhan, Pratap Kumar Mathur
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 228-249
Technical Paper | Decontamination/Decommissioning | doi.org/10.13182/NT98-A2865
N2-BET Surface Area Measurements on Crushed and Intact Minerals and Rocks: A Proposal for Estimating Sorption Transfer Factors
Michael H. Bradbury, Bart Baeyens
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 250-253
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT98-A2866
Criticality Analysis of the Multiplying Material Inside the Chernobyl Sarcophagus
Marko Maucec, Matjaz Ravnik, Bogdan Glumac
Nuclear Technology | Volume 122 | Number 3 | June 1998 | Pages 255-264
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2867
Nonuniformity Effect on Reactivity of Fuel in Slurry
Hiroshi Okuno, Tomohiro Sakai
Nuclear Technology | Volume 122 | Number 3 | June 1998 | Pages 265-275
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2868
Fission Gas Release Determination Using an Anti-Compton Shield Detector
Ingvar Matsson, Björn Grapengiesser, Peter Jansson, Ane Håkansson, Anders Bäcklin
Nuclear Technology | Volume 122 | Number 3 | June 1998 | Pages 276-283
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT98-A2869
Analysis of Turbulent Mixing in Rod Bundles with an Anisotropic Turbulent Diffusion Model Based on the Flow Pulsation Phenomenon
Sin Kim, Goon Cherl Park
Nuclear Technology | Volume 122 | Number 3 | June 1998 | Pages 284-294
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2870
Comparative Mass and Energy Release and Containment Analyses for a Large-Break Loss-of-Coolant Accident Using RELAP5/CONTEMPT4 and Design Computer Codes
Young Min Kwon, Chan Eok Park, Jin Ho Song
Nuclear Technology | Volume 122 | Number 3 | June 1998 | Pages 295-305
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT98-A2871
A Structured Methodology for Waste Management Facility Accident Analysis
Charles J. Mueller, Stephen M. Folga, Jordi Roglans-Ribas, Bassel Nabelssi, Jofu Mishima
Nuclear Technology | Volume 122 | Number 3 | June 1998 | Pages 306-317
Technical Paper | Criticality of Nuclear Materials | doi.org/10.13182/NT98-A2872
Design of a Fuzzy Logic Controller for Water Level Control in an Advanced Boiling Water Reactor Based on Input-Output Data
Chaung Lin, Dih-Hua Yang
Nuclear Technology | Volume 122 | Number 3 | June 1998 | Pages 318-329
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT98-A2873
Nuclear Applications of Accelerator-Driven Spallation Targets
Gregory J. Van Tuyle
Nuclear Technology | Volume 122 | Number 3 | June 1998 | Pages 330-354
Technical Paper | Accelerators | doi.org/10.13182/NT98-A2874
