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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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INL’s new innovation incubator could link start-ups with an industry sponsor
Idaho National Laboratory is looking for a sponsor to invest $5 million–$10 million in a privately funded innovation incubator to support seed-stage start-ups working in nuclear energy, integrated energy systems, cybersecurity, or advanced materials. For their investment, the sponsor gets access to what INL calls “a turnkey source of cutting-edge American innovation.” Not only are technologies supported by the program “substantially de-risked” by going through technical review and development at a national laboratory, but the arrangement “adds credibility, goodwill, and visibility to the private sector sponsor’s investments,” according to INL.
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A Parametric Study of the Steady-State Operational Characteristics of the Ohio State University Natural Circulation, Indirect-Cycle, Inherently Safe Boiling Water Reactor
Hikmet S. Aybar, Tunc Aldemir, Richard N. Christensen
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 1-22
Technical Paper | Fission Reactor | doi.org/10.13182/NT95-A35140
An Estimation of Core Damage Frequency of a Pressurized Water Reactor During Midloop Operation Due to Loss of Residual Heat Removal
Chun-Chang Chao, Chi Ta Chen, Min Lee
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 23-33
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35141
A Comparison of the RELAP5/MOD3 Code with the IIST Natural Circulation Experiments
Yuh-Ming Ferng, Chien-Hsiung Lee
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 34-45
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35142
Predicting the Severity of Nuclear Power Plant Transients Using Nearest Neighbors Modeling Optimized by Genetic Algorithms on a Parallel Computer
Jie Lin, Yair Bartal, Robert E. Uhrig
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 46-62
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35143
Effects of Different Parameters on the Densities of Uranium Dioxide and Uranium Dioxide-Gadolinium Oxide Fuels Produced by the Sol-Gel Technique
G. Gündüz, İ. Uslu, I. Önal, H. H. Durmazuçar, T. Öztürk, A. A. Akşit, B. Kopuz, F. Can, Ş. Can, R. Uzmen
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 63-69
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35144
Measured Insensitivity of Memory Devices to Various Nuclear Radiations
Alireza Behbahani, James N. Anno
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 70-79
Technical Paper | Material | doi.org/10.13182/NT95-A35145
Evaporation Reduction from Tritiated Water Pools
M. T. Pauken, M. F. Dowling, B. K. Kamboj, S. M. Jeter, S. I. Abdel-Khalik
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 80-91
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35146
Application of Detonation Wave Theory to Subcritical Vapor Explosions
Luder Tibkin, Mahmoud El-Beshbeeshy, Riccardo Bonazza, Michael L. Corradini
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 92-104
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35147
Failed Fuel Detection in Reactor Coolant Using Radioiodine Measurement
R. K. Gopalakrishnan, P. M. Ravi, S. K. Prasad, M. R. Iyer
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 105-108
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35148
Nuclear Fuel Management Optimization Using Genetic Algorithms
Michael D. DeChaine, Madeline Anne Feltus
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 109-114
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35149
Application of Reliability-Centered Maintenance to Boiling Water Reactor Emergency Core Cooling Systems Fault-Tree Analysis
Young A. Choi, Madeline Anne Feltus
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 115-121
Technical Note | Reactor Operation | doi.org/10.13182/NT95-A35150
Neutronics and Engineering Design of the Aqueous-Slurry Accelerator Transmutation of Waste Blanket
Carl A. Beard, John J. Buksa, Michael W. Cappiello, J. Wiley Davidson, Jay S. Elson, John R. Ireland, Robert A. Krakowski, Burt J. Krohn, William C. Sailor, Joseph L. Sapir
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 122-132
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35151
Long-Lived Waste Transmutation in Reactors
Jean Tommasi, Marc Delpech, Jean-Paul Grouiller, Alain Zaetta
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 133-148
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT111-133
Transmutation of High-Level Radioactive Waste by a Charged-Particle Accelerator
Hiroshi Takahashi
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 149-162
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT95-A35153
Vitrification of Fission Product Solutions: Investigation of the Effects of Noble Metals on the Fabrication and Properties of R7T7 Glass
M. Puyou, N. Jacquet-Francillon, J. P. Moncouyoux, C. Sombret, F. Teulon
Nuclear Technology | Volume 111 | Number 1 | July 1995 | Pages 163-168
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT95-A35154
Estimation and Interpretation of keff Confidence Intervals in MCNP
Todd J. Urbatsch, R. Arthur Forster, Richard E. Prael, Richard J. Beckman
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 169-182
Technical Paper | Nuclear Criticality Safety Special / Fission Reactor | doi.org/10.13182/NT95-A35128
Validation of KENO V.a with ENDF/B-V Cross Sections for 233U Systems
M. E. Dunn, B. Basoglu, C. L. Bentley, C. Haught, M. J. Plaster, A. D. Wilkinson, T. Yamamoto, H. L. Dodds
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 183-196
Technical Paper | Nuclear Criticality Safety Special / Fission Reactor | doi.org/10.13182/NT95-A35129
Analyses of Hypothetical Nuclear Criticality Excursions in 10- and 20-MW Freezer/Sublimer Vessels
Chris F. Haught, W. C. Jordan, B. Basoglu, R. W. Brewer, A. D. Wilkinson, H. L. Dodds
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 197-218
Technical Paper | Nuclear Criticality Safety Special / Nuclear Criticality Safety | doi.org/10.13182/NT95-A35130
Analysis of a Hypothetical Criticality Accident in a Waste Supercompactor
M. J. Plaster, B. Basoglu, C. L. Bentley, M. E. Dunn, A. E. Ruggles, A. D. Wilkinson, T. Yamamoto, H. L. Dodds
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 219-226
Technical Paper | Nuclear Criticality Safety Special / Nuclear Criticality Safety | doi.org/10.13182/NT95-A35131
Improved Dose Estimates for Nuclear Criticality Accidents
Alan D. Wilkinson, B. Basoglu, C. L. Bentley, M. E. Dunn, Chris F. Haught, M. J. Plaster, T. Yamamoto, H. L. Dodds, Calvin M. Hopper
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 227-240
Technical Note | Nuclear Criticality Safety Special / Nuclear Criticality Safety | doi.org/10.13182/NT95-A35132
Thermal Hydraulics of an External Water Wall Type Passive Containment Cooling System
Yoshiyuki Kataoka, Michio Murase, Tadashi Fujii, Kenji Tominaga
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 241-250
Technical Paper | Nuclear Criticality Safety Special / Fission Reactor | doi.org/10.13182/NT95-A35133
Dynamic Stability of a Fluidized-Bed Nuclear Reactor
Volnei Borges, Marco Túllio De Vilhena
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 251-259
Technical Paper | Nuclear Criticality Safety Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A35134
Failure Mechanisms of Fuel Particle Coating for High-Temperature Gas-Cooled Reactors During the Coating Processes
Kazuo Minato, Hironobu Kikuchi, Kousaku Fukuda, Nobuyuki Suzuki, Hiroshi Tomimoto, Nobu Kitamura, Mitsunobu Kaneko
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 260-269
Technical Paper | Nuclear Criticality Safety Special / Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35135
Three-Dimensional Neutron Flux Calculations for the VVER Pressure Vessel
Sergey I. Belousov, Krassimira D. Ilieva, Stoyan Y. Antonov
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 270-274
Technical Paper | Nuclear Criticality Safety Special / Material | doi.org/10.13182/NT95-A35136
Flashing and Heat Transfer During Outsurge Transients in a Small Pressurizer
Mario De Salve, Giovanni Del Tin, Bruno Panella
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 275-282
Technical Paper | Nuclear Criticality Safety Special / Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35137
Use of a Real-Time RELAP5 Model to Dynamically Test a Digital Feedwater Control System for a Boiling Water Reactor
J. A. Mowrey, S. I. Abdel-Khalik, K. W. Ross
Nuclear Technology | Volume 111 | Number 2 | August 1995 | Pages 283-302
Technical Paper | Nuclear Criticality Safety Special / Reactor Operation | doi.org/10.13182/NT95-A35138
Confinement of the Radiological Source Term During Beyond-Design-Basis Events in Future Pressurized Water Reactors
Guenther Kessler, Bernhard Kuczera, Joachim Ehrhardt, Georg Henneges, Werner Scholtyssek, Hans-Werner Wiese
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 305-318
Technical Paper | A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A15861
Long-Term Containment Thermal-Hyraulic Loads in Pressurized Water Reactor Core-Melt Accidents
Werner Scholtyssek
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 319-330
Technical Paper | A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A15862
Studies for the Staggered Pans Core Catcher
Günter Fieg, Manfred Möschke, Heinrich Werle
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 331-340
Technical Paper | A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A15863
Transient Experiments with Thermite Melts for a Core Catcher Concept Based on Water Addition from Below
Walter Tromm, Hans Alsmeyer
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 341-350
Technical Paper | A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A15864
Dynamic Loads from Reactor Pressure Vessel Core Melt-Through Under High Primary System Pressure
Günter Jacobs
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 351-357
Technical Paper | A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A15865
Severe Accident Containment Loads and Possible Design Concepts of Future Large Pressurized Water Reactors
Guenther Kessler, Josef Eibl
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 358-368
Technical Paper | A New Light Water Reactor Safety Concept Special / Fission Reactor | doi.org/10.13182/NT95-A15866
Slug Impact Loading on the Vessel Head During a Postulated In-Vessel Steam Explosion in Pressurized Water Reactors—Assessments and Discussion of the Investigation Strategy
R. Krieg, T. Malmberg, G. Messemer, T. Stach, E. Stratmanns
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 369-385
Technical Paper | A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A15867
Passive Containment Cooling by Natural Air Convection
Franz-Josef Erbacher, Hans-Joachim Neitzel
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 386-394
Technical Paper | A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A15868
Containment Pressure Loads from Hydrogen Combustion in Unmitigated Severe Accidents
W. Breitung, R. Redlinger
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 395-419
Technical Paper | A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A15869
A Model for Structural Response to Hydrogen Combustion Loads in Severe Accidents
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 420-425
Technical Paper | A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A15870
Feasibility Study for a Containment to Resist Core-Melt Accidents
Josef Butsch, Franz-Hermann Schlüter, Josef Eibl
Nuclear Technology | Volume 111 | Number 3 | September 1995 | Pages 426-436
Technical Paper | A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety | doi.org/10.13182/NT95-A15871
