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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
Marco Island, FL|JW Marriott Marco Island
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
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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EROS: An Experimental Breeder Reactor II Operational Safety Code
E. M. Dean, H. A. Larson
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 7-19
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A16182
Sensitivity and Uncertainty Analysis of the Coupled Fast Reactivity Measurements Facility Central Flux Spectrum
John M. Ryskamp, Robert A. Anderl, B. L. Broadhead, W. E. Ford III, J. L. Lucius, J. H. Marable, J. J. Wagschal
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 20-35
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A16183
RETRAN Analysis of the Turbine Trip Tests Performed at the Peach Bottom Atomic Power Station Unit 2
Karl Hornyik, Joseph A. Naser
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 36-49
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A16184
Environmental Gamma-Ray Measurement Methods for French Nuclear Installation Impact Studies
D. Gauthier, C. Caput, F. Bourdeau
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 50-57
Technical Paper | Nuclear Safety | doi.org/10.13182/NT82-A16185
Boiling Water Reactor Cycle Extension Operation
George C. Fullmer
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 58-64
Technical Paper | Fuel Cycle | doi.org/10.13182/NT82-A16186
High Temperature Postirradiation Materials Performance of Spent Pressurized Water Reactor Fuel Rods Under Dry Storage Conditions
Robert E. Einziger, Sharon D. Atkin, David E. Stellrecht, V. Pasupathi
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 65-80
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A16187
Mol-7B—An 18-Pin Bundle Operating 200 Days Beyond Breach
Peter Weimar, Wolfgang Ernst
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 81-89
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A16188
Combination of Fuel-Cladding Chemical and Mechanical Interactions in Mixed Oxide Fuel Pins
O. Götzmann
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 90-103
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A16189
Fuel Chemistry Impact on Vented Fuel Pin Design
C. E. Johnson, S. W. Tam, P. E. Blackburn, D. C. Fee
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 104-113
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A16190
Heat Treatment of Cr—1 Mo Steel for Breeder Reactor Steam Generators
R. L. Klueh
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 114-124
Technical Paper | Material | doi.org/10.13182/NT82-A16191
Measurement of Thermal Power Density Distributions by Fuel Pin Gamma Scanning
J. T. Dawson, G. Smith
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 125-133
Technical Paper | Technique | doi.org/10.13182/NT82-A16192
An Assessment of TRAC-PD2 Refill Calculations Based on Creare Countercurrent Flow Tests
T. F. Bott
Nuclear Technology | Volume 57 | Number 1 | April 1982 | Pages 134-139
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT82-A16193
A Liquid-Metal Fast Breeder Reactor Core Design with Seed Blanket Modular Assemblies
Bal Raj Sehgal, Ching-Lu Lin, Edward L. Fuller
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 149-162
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A26277
Dynamic Analysis of the Condensate Feedwater System in Boiling Water Reactor Plants
Junichi Tanji, Takashi Omori
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 163-174
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A26278
Experimental Modeling of Hydrogen Evolution Rates from Surfaces with Exposed Aluminum in Contact with Containment Sprays in Pressurized Water Reactor Nuclear Power Plants
L. E. S. Smith, R. O. Lane, P. V. Guthrie
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 175-178
Technical Paper | Nuclear Safety | doi.org/10.13182/NT82-A26279
ROSA-III Base Test Series for a Large Break Loss-of-Coolant Accident in a Boiling Water Reactor
K. Tasaka, M. Shiba, Y. Koizumi, Y. Anoda, N. Abe
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 179-191
Technical Paper | Nuclear Safety | doi.org/10.13182/NT82-A26280
Characteristics and Behavior of Emulsion at Nuclear Fuel Reprocessing
Kozo Gonda, Koichiro Oka, Takeshi Nemoto
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 192-202
Technical Paper | Chemical Processing | doi.org/10.13182/NT82-A26281
ELESTRES: A Finite Element Fuel Model for Normal Operating Conditions
Henry H. Wong, Ertugrul Alp, W. R. Clendening,+ M. Tayal,+, Lloyd R. Jones
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 203-212
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26282
Determination of Thermal Accommodation Coefficients of Helium, Argon, and Xenon on a Surface of Zircaloy-2 at About 25°C
Lloyd B. Thomas, Sudarshan K. Loyalka
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 213-219
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26283
A Model for Gap Conductance in Nuclear Fuel Rods
Sudarshan K. Loyalka
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 220-227
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26284
Cost and Other Effects of Reduced Fuel Pellet Diameters
David J. Dixon, Mohamed A. Elmaghrabi, Ian C. Rickard
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 228-233
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26285
Bend Testing for Miniature Disks
Fan Hsiung Huang, Margaret L. Hamilton, Gary L. Wire
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 234-242
Technical Paper | Material | doi.org/10.13182/NT82-A26286
Gamma Treatment of Sewage Sludge with Spent Nuclear Fuel
Norberto Piccinini, Rodolfo Simonetto, Giovanni Del Tin
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 243-254
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT82-A26287
Scaling Laws of Transient Heat and Mass Flow for Modeling the Loss-of-Coolant Accident
S. Benedek
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 255-263
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT82-A26288
Flow Measurement in Sodium and Water Using Pulsed-Neutron Activation: Part 1, Theory
Howard A. Larson, Charles C. Price, Robert N. Curran, John I. Sackett
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 264-271
Technical Paper | Analyse | doi.org/10.13182/NT82-A26289
Flow Measurement in Sodium and Water Using Pulsed-Neutron Activation: Part 2, Experiment
Charles C. Price, Howard A. Larson, Robert N. Curran, John I. Sackett
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 272-284
Technical Paper | Analyse | doi.org/10.13182/NT82-A26290
Application of an Ion Exchange Method for Sensitivity Improvement of an Automated Radionuclide Analysis System
Hiromi Tokoi, Hiroshi Kitaguchi, Masaaki Fujii, Katsuhiro Mizuno, Akira Ishizuka, Toyonori Kudou, Akira Ogushi
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 285-291
Technical Paper | Analyse | doi.org/10.13182/NT82-A26291
Analytical Approximations for the Long-Term Decay Behavior of Spent Fuel and High-Level Waste
Carl M. Malbrain, Richard K. Lester, John M. Deutch
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 292-305
Technical Paper | Education | doi.org/10.13182/NT82-A26292
Authors
G. B. Barton, R. F. Keough, J. J. McCown, J. A. Yount, David C. Cox, Paul Baybutt, Gert Sdouz, Sigurdur J. Dagbjartsson, Timm Preusser, Tsutomu Yokoyama, Toshiyuki Tamura, T. N. Tiegs, Tjalle T. Vandergraaf, Debbie R. M. Abry, B. A. Cheadle, C. E. Coleman, H. Licht, Bryan A. Chin, Robert J. Neuhold, Jerry L. Straalsund, Kiyoshi Sakurai
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 311-314
Department | doi.org/10.13182/NT82-A26299
Developments in Electrochemical Oxygen Meter Probes for Use in Liquid Sodium
G. B. Barton, R. F. Keough, J. J. McCown, J. A. Yount
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 315-319
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A26300
Limit Lines for Risk
David C. Cox, Paul Baybutt
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 320-330
Technical Paper | Nuclear Safety | doi.org/10.13182/NT82-A26301
An Analytical Study of Azimuthal Temperature Distribution in Pressurized Water Reactor Fuel Rods Under Steady-State and Blowdown Conditions
Gert Sdouz, Sigurdur J. Dagbjartsson
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 331-342
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26302
Modeling of Carbide Fuel Rods
Timm Preusser
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 343-371
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26303
Neutron Emission Characteristics of Spent Boiling Water Reactor fuel
Tsutomu Yokoyama, Toshiyuki Tamura
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 372-388
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26304
Fission Product Pd-SiC Interaction in Irradiated Coated-Particle Fuels
T. N. Tiegs
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 389-398
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26305
Radionuclide Sorption on Drill Core Material from the Canadian Shield
Tjalle T. Vandergraaf, Debbie R. M. Abry
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 399-412
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A26306
CANDU-PHW Pressure Tubes: Their Manufacture, Inspection, and Properties
B. A. Cheadle, C. E. Coleman, H. Licht
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 413-425
Technical Paper | Material | doi.org/10.13182/NT82-A26307
Materials Development for Fast Breeder Reactor Cores
Bryan A. Chin, Robert J. Neuhold, Jerry L. Straalsund
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 426-435
Technical Paper | Material | doi.org/10.13182/NT82-A26308
Measurement of Neutron Fluence Above 0.1 MeV with the Dosimeter 93Nb(n,n')93mNb
Kiyoshi Sakurai
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 436-441
Technical Paper | Analyse | doi.org/10.13182/NT82-A26309
Textbook of Radiotherapy
Robert S. Heusinkveld
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Page 442
Department | Book Review | doi.org/10.13182/NT82-A26313
Introduction to Nuclear Reactions
W. Morris Farr
Department | Book Review | doi.org/10.13182/NT82-A26314
Thermal Radiation Heat Transfer (2nd Edition)
M. R. Bottaccini
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Page 443
Department | Book Review | doi.org/10.13182/NT82-A26310
Transitional Energy Policy 1980–2030
K. Almenas
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Pages 443-444
Department | Book Review | doi.org/10.13182/NT82-A26311
Ion Chambers for Neutron Dosimetry (Radiation Protection)
J. N. Anno
Nuclear Technology | Volume 57 | Number 3 | June 1982 | Page 445
Department | Book Review | doi.org/10.13182/NT82-A26312
