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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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The Effect of Coolant Orificing on the Core Performance of a Heterogeneous Liquid-Metal Fast Breeder Reactor
Mamoru Konomura, Yoshiaki Oka, Shigehiro An
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 7-16
Technical Paper | Fission Reactor | doi.org/10.13182/NT83-A33138
An Emergency Measurement System for the Rapid Assessment of Environmental Exposure
Karl Heinemann, Ralf Hille, Kurt Jürgen Vogt
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 17-24
Technical Paper | Nuclear Safety | doi.org/10.13182/NT83-A33139
Simple Reactor Model Simulation of a LOFT ATWS Event
J. Louis Tylee
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 25-32
Technical Paper | Nuclear Safety | doi.org/10.13182/NT83-A33140
Evaluation of Volatile and Gaseous Fission Product Behavior in Water Reactor Fuel Under Normal and Severe Core Accident Conditions
Jeffrey Rest
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 33-48
Technical Paper | Nuclear Safety | doi.org/10.13182/NT83-A33141
A Modified Borresen Coarse-Mesh Computation for a Three-Dimensional Pressurized Water Reactor Benchmark Problem
Chang Hyo Kim, Samuel H. Levine
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 49-54
Technical Paper | Fuel Cycle | doi.org/10.13182/NT83-A33142
Development of a Process for the Co-Conversion of Pu-U Nitrate Mixed Solutions to Mixed-Oxide Powder Using a Microwave Heating Method
Masumichi Koizumi, Katsuyuki Ohtsuka, Hiroto Isagawa, Hideo Akiyama, Akio Todokoro
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 55-70
Technical Paper | Chemical Processing | doi.org/10.13182/NT83-A33143
Mass Spectrometric Study of the Potential of Al2O3/SiO2 Additives for the Retention of Cesium in Coated Particles
K. Hilpert, R. Odoj, H. W. Nürnberg
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 71-77
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33144
An Automated Procedure for Selecting Boiling Water Reactor Refueling Policies Following Operational Problems or Changes
S. H. Yeh, Alice Y. Ying, J. Weisman
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 78-92
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33145
Decontamination of Radioactive Metal Surfaces by Plasma Arc Gouging
Osamu Kuriyama, Takao Koyama, Makoto Kikuchi
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 93-99
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33146
Effect of Helium Pressure on the Response of Unirradiated UO2 Subjected to Thermal Transients
G. R. Fenske, R. B. Poeppel, J. E. Emerson, P. M. Chapello, S. G. Das, R. H. Sevy
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 100-112
Technical Paper | Material | doi.org/10.13182/NT83-A33147
Temperature-Dependent Microhardness of A533-B Reactor Pressure Vessel Steels
Bryce L. Shriver, Thomas G. Hook
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 113-117
Technical Paper | Material | doi.org/10.13182/NT83-A33148
Investigations on the Improvement of the Iodine Filtration Concept of Pressurized Water Reactors
H. Deuber, J. G. Wilhelm
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 118-120
Technical Note | Nuclear Safety | doi.org/10.13182/NT83-A33149
A Liquid-Metal Fast Breeder Reactor Fueling Concept for Thorium Utilization and Improved Inherent Safety
Yuji Ishiguro
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 121-126
Technical Note | Fuel Cycle | doi.org/10.13182/NT83-A33150
Method for the Sealing and Decontamination of Radioactive and Radioactively Contaminated Components and Materials
Daniel Neupert, Peter Demtröder
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 127-128
Technical Note | Radioactive Waste Management | doi.org/10.13182/NT83-A33151
RETRAN Overview
Lance J. Agee
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 143-152
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33186
RETRAN Nonequilibrium Two-Phase Flow Model for Operational Transient Analyses
M. P. Paulsen, E. D. Hughes
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 153-166
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33187
Numerical Solution Method Improvements for RETRAN
E. D. Hughes, K. R. Katsma
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 167-180
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33188
RETRAN-02 Calculations of Operational Transients in the Loss-of-Fluid Test Facility
Clayton S. Miller, James Robert White, Richard D. Hentzen
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 181-192
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33189
RETRAN Safety Analyses of the Nuclear-Powered Ship Mutsu
Yoshinori Naruko, Toshihisa Ishida, Yoshimi Tanaka, Yoshiaki Futamura
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 193-204
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33190
Prediction of GE-Atlas Transient Boiling Transition Data Using RETRAN-02/RETRAN-15F
A. A. Farooq Ansari, Kevin J. Burns, Douglas K. Beller, Quazi A. Haque, Stephen P. Schultz
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 205-211
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33191
RETRANS’s Role in the Development of Northeast Utilities’ Analytical Capabilities
Mario V. Bonaca, Albert Gharakhani, Richard W. Sterner
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 212-223
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33192
RETRAN-02 and DYNODE-P Analyses of a Steam Generator Tube Break Transient
Jason Chao, V. K. (Bindi) Chexal, William H. Layman, David A. Rautmann, Craig E. Peterson, Larry W. Cress
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 224-237
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33193
RETRAN-02 Analysis of Arkansas Nuclear One Unit 2 Tests
Salvador Ranatza, Jr.
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 238-252
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33194
RETRAN Analyses for Improving Plant Procedures and Operator Training
T. Gary Broughton, N. G. Trikouros
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 253-259
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33195
LOFTRAN/RETRAN Comparison Calculations for a Postulated Loss-of-Feedwater ATWS in the Sizewell ‘B’ PWR
Karel L. Papez, Daniel H. Risher
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 260-275
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33196
Qualification of a RETRAN-02 Model for Boiling Water Reactor Transient Analysis
Michael E. Garrett, Samuel L. Forkner, T. A. Keys, George W. Perry, M. Wesley Waddell, Jr.
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 276-295
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33197
Boiling Water Reactor Stability Analysis with RETRAN
Karl Hornyik
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 296-312
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33198
Evaluation of RETRAN-02 Options with Peach Bottom Data
Joseph A. Naser
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 313-328
Technical Paper | Second International RETRAN Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33199
Simplified Tornado Depressurization Design Methods for Nuclear Power Plants
Neil M. Howard, Mitchell J. Krasnopoler
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 329-337
Technical Paper | Second International RETRAN Meeting / Fission reactor | doi.org/10.13182/NT83-A33200
Deactivation of Silver Zeolite Adsorbers by Airborne Organics
Lawrence A. Casper, Arvid M. Jensen, Kendall G. Magill, Penny M. Wikoff
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 338-343
Technical Paper | Second International RETRAN Meeting / Nuclear Safety | doi.org/10.13182/NT83-A33201
Analysis of Creep for Nuclear Waste Storage in a Salt Formation
William T. Li, Ching L. Wu
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 344-352
Technical Paper | Second International RETRAN Meeting / Radioactive Waste Management | doi.org/10.13182/NT83-A33202
Optimal Step Assays and Flow Rates in Gaseous Diffusion Squared-Off Cascades for Uranium Enrichment
Osvaldo Fiorella, Manlio Mangia, Elio Oliveri
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 353-361
Technical Paper | Second International RETRAN Meeting / Radioisotopes and Isotope | doi.org/10.13182/NT83-A33203
Evaluation of Potential Head-End Procedures for Graphite-Containing Fuel Elements
Norbert G. Hoogen, Erich R. Merz
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 380-387
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Chemical Processing | doi.org/10.13182/NT83-A33160
Reprocessing in Breeder Fuel Cycles
William D. Burch, W. S. Groenier
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 388-397
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel | doi.org/10.13182/NT83-A33161
Reprocessing of Plutonium-Enriched Light Water Reactor Fuels
E. J. Detilleux, Werner Hild, L. Geens
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 398-402
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel | doi.org/10.13182/NT83-A33162
Irradiation Performance of Advanced Coated Particles for High-Temperature Gas-Cooled Reactor Fuel Cycles
Rainer P. Conrad, Cesare Merlini, Alfred-W. Mehner
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 403-415
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel | doi.org/10.13182/NT83-A33163
Plutonium-Enriched Thermal Fuel Production Experience in Belgium
J. M. Leblanc
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 416-422
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel | doi.org/10.13182/NT83-A33164
The Radioactive Waste Management Program of the Commission of the European Communities: Past, Present, and Future Trends
Serge M. Orlowski
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 423-431
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33165
Incentives for Integrating an Alpha Waste Management Strategy into the Fuel Cycle
Heinz Dworschak, Brian A. Hunt, Francesco Mannone, Francis Mousty
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 432-443
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33166
Methodology for a Consequence Analysis of a Nuclear Waste Disposal Facility
Bernd K. Buchheim, Hans Bunschi, and, Franz J. Hoop, James Fitzpatrick
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 444-449
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33167
The Decontamination of Soft-Plated Nickel Surfaces Compared to Alternative Surface Materials Used in Radioactive Transport and Storage Containers
Hans-Urs Zwicky, Ian M. Böhringer,*, Ferdinand Petrik, Dieter O. Bedenig
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 450-454
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33168
Nuclear Waste Management Policy in France
Jean F. Lefevre
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 455-459
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33169
Highly Dense Graphite Matrix: A New Material for the Conditioning of Radioactive Wastes
Milan Hrovat, Karl-Gerhard Hackstein, Hans Huschka, H. A. Pirk, Thomas Schmidt-Hansberg
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 460-464
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33170
A Computer Program for Assessment of Emergency Operation Procedures Under Non-LOCA Transient Conditions in BWRs
Yukiharu Ohga
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 465-474
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Safety | doi.org/10.13182/NT83-A33171
Diffusion of Silver and Cesium in Silicon-Carbide Coatings of Fuel Particles for High-Temperature Gas-Cooled Reactors
Winfried Amian, Detlev Stöver
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 475-486
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel | doi.org/10.13182/NT61-475
Optimized Depletion of Lumped Burnable Poisons in Pressurized Water Reactors
Ziad H. Kodah, Samuel H. Levine
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 487-495
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel | doi.org/10.13182/NT83-A33173
The Significance of Leach Rates in Determining the Release of Radioactivity from Vitrified Nuclear Waste
Antony E. Hughes, J. Angwin C. Marples, A. Marshall Stoneham
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 496-502
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33174
Actinide Hazard Reduction by Partitioning and Transmutation in a Coupled Reactor System
Alireza Haghighat, Maurice A. Robkin
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 503-513
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33175
Measured Thermal Response of Full-Scale Spent Fuel Cask to a Torch Environment
Manuel G. Vigil, Amado A. Trujillo, H. Richard Yoshimura
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 514-520
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management | doi.org/10.13182/NT83-A33176
Preliminary Study of Cost Benefits Associated with Duplex Fuel Pellets of the LOWI Type
John Brian Ainscough*, David Norman Coucill, David Anthony Howl, Arne Jensen, Ib Misfeldt
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 521-532
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Economic | doi.org/10.13182/NT83-A33177
Radiation-Induced Gas Evolution from Commercial Lubricant Base Oil
Kazuo Arakawa, Naohiro Hayakawa, Hiroshi Nakanishi
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 533-539
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Material | doi.org/10.13182/NT83-A33178
Generalization of Radioiodine Adsorption on Geological Materials
Toshiaki Ohe, Akira Nakaoka
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 540-546
Technical Paper | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radiation Biology and Environment | doi.org/10.13182/NT83-A33179
Digital Simulation of the Pressurizer in a Pressurized Water Nuclear Reactor
V. V. Athani, L. Vijaykumar
Nuclear Technology | Volume 61 | Number 3 | June 1983 | Pages 547-549
Technical Note | New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33180
