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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
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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The Abundance of Fission Gases in the Off Gas of a Boiling Water Reactor
H. W. Kalfsbeek
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 7-21
Technical Paper | Fission Reactor | doi.org/10.13182/NT83-A33227
The Modular High-Temperature Reactor
Herbert Reutler, Günter H. Lohnert
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 22-30
Technical Paper | Fission Reactor | doi.org/10.13182/NT83-A33228
An Analytical Study of a Small-Break Loss-of-Coolant Accident with Upper Head Injection
Mark T. Leonard
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 31-42
Technical Paper | Nuclear Safety | doi.org/10.13182/NT83-A33229
Simple Lake Breeze Front Position Technique for Off-Site Dose Assessment
Thomas J. Burda, Carl A. Mazzola
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 43-50
Technical Paper | Nuclear Safety | doi.org/10.13182/NT83-A33230
Modeling Fragmentation and Spallation of Oxide Reactor Fuel During Transient Heating Including the Effects of Burnup and Fission Product Distribution
Ronald J. DiMelfi, John M. Kramer
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 51-61
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33231
Heat Transfer from Transport Cask Storage Facilities for Spent Fuel Elements
Wolfgang von Heesen, Heinz Malmström, Rüdiger Detzer, Werner Loew
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 62-70
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33232
Evaluation of SrMoO4 in Repository Simulating Tests
Sridhar Komarneni, Rustum Roy, Della M. Roy
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 71-74
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33233
Irradiation Behavior of Pressurized Water Reactor Control Materials
Richard V. Demars, Charles G. Dideon, Thomas A. Thornton, James S. Tulenko, Wayne A. Pavinich, Elma Beth S. Pardue*
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 75-80
Technical Paper | Material | doi.org/10.13182/NT83-A33234
Dose Response in Radiation-Induced Human Carcinogenesis: Accumulated Data Do Not Yet Solve the Enigma
Werner Burkart
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 81-93
Technical Paper | Radiation Biology and Environment | doi.org/10.13182/NT83-A33235
Statistical Characteristics of Incipient Two-Phase Noise for Reactor Diagnosis
Monideep Kumar De
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 94-101
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33236
Development and Operational Experiences of an Automated Remote Inspection System for Interior of Primary Containment Vessel of a BWR
Norihiko Ozaki, Fumio Tomizawa, Masaaiki Fujii, Masayoshi Sasaki, Ken-Ichiro Sadakane, Chikara Sato, Katsuhiro Mizuno
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 102-109
Technical Paper | Technique | doi.org/10.13182/NT83-A33237
The Movement of a Redox Front Downstream from a Repository For Nuclear Waste
Ivars Neretnieks
Nuclear Technology | Volume 62 | Number 1 | July 1983 | Pages 110-115
]Technical Note | Radioactive Waste Management | doi.org/10.13182/NT83-A33238
The Effect of Salt Composition on Reductive Extraction of Some Typical Elements from Molten LiF-BeF2 Salt into Liquid Bismuth
Hirotake Moriyama, Kunimitsu Yajima, Yasunobu Tominaga, Kimikazu Moritani, Jun Oishi
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 133-138
Technical Paper | Chemical Processing | doi.org/10.13182/NT83-A33211
The Current Status and Perspectives of Fissile Material Availability in The World Through the Year 2000
John Jeffrey Stobbs, Antonio Matteo Taormina
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 139-144
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33212
Aqueous Corrosion of Uranium Aluminide Fuel
Krishna Vinjamuri, Richard R. Hobbins
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 145-150
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33213
The Effects of Surface Area to Solution Volume on Waste Glass Leaching
L. R. Pederson, C. Q. Buckwalter, G. L. McVay
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 151-158
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33214
Transient Analysis of the Three Mile Island Unit 2 Pressurizer System
Benaissa Baggoura, William R. Martin
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 159-171
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33215
Safety Analysis of the Reactivity Transients Resulting from Water Ingress into a High-Temperature Pebble Bed Reactor
Rahim Nabbi, Wilfried Jahn, Gerhard Meister, Werner Rehm
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 172-189
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33216
Analysis of Decommissioning Costs for Nuclear Power Reactors
David F. Greenwood, Richard K. Westfahl, James W. Rymsha
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 190-206
Technical Paper | Economic | doi.org/10.13182/NT83-A33217
Analysis of Detailed Neutron Fluxes in a PWR Pressure Vessel by Two- and Three-Dimensional Pallas Transport Codes
Kiyoshi Takeuchi, Nobuo Sasamoto
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 207-221
Technical Paper | Analyse | doi.org/10.13182/NT83-A33218
A Finite Difference Treatment of Differential Equation Systems with Widely Differing Time Constants
G. Ronald Dalton, Michael T. Gamble
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 222-226
Technical Paper | Analyse | doi.org/10.13182/NT83-A33219
System Preparation and Fast Neutron Spectra Measurement in a Graphite Stack
Alex Tsechanski, Gad Shani
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 227-237
Technical Paper | Analyse | doi.org/10.13182/NT83-A33220
Modified Fuel Assembly Design for Pressurized Water Reactors with Improved Fuel Utilization
Alex Galperin, Yigal Ronen
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 238-242
Technical Note | Fuel Cycle | doi.org/10.13182/NT83-A33221
Deposition of Model Crud on Boiling Zircaloy Surfaces at High Temperature
Mitsuo Kawaguchi, Kenkichi Ishigure, Norihiko Fujita, Keichi Oshima
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 253-262
Technical Paper | Fission Reactor | doi.org/10.13182/NT83-A33249
A Transient Model for the Ablation and Decomposition of Concrete
Michael L. Corradini
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 263-273
Technical Paper | Nuclear Safety | doi.org/10.13182/NT83-A33250
High Converter Pressurized Water Reactor with Heavy Water as a Coolant
Yigal Ronen, Dror Regev
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 274-283
Technical Paper | Fuel Cycle | doi.org/10.13182/NT83-A33251
The Lifetime and Failure Strain Prediction of Zircaloy-4 Cladding Loaded Under Loca-Similar Temperature Ramp Conditions
Michael Boček, Claus Petersen, Lothar Schmidt
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 284-297
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33252
Plutonium Speciation in Selected Basalt, Granite, Shale, and Tuff Groundwaters
Jess M. Cleveland, Terry F. Rees, Kenneth L. Nash
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 298-310
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33253
Effects of Temperature on the Leaching Behavior of Sintered Modified Synroc-B Waste form
A. G. Solomah
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 311-316
Technical Paper | Material | doi.org/10.13182/NT83-A33254
Analysis of Uranium Isotope Separation by Redox Chromatography
Sachio Fujine, Yuji Naruse, Koreyuki Shiba
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 317-324
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT83-A33255
The Effect of Vacuum Core Boundary Conditions on Separation in the Gas Centrifuge
ED Von Halle, Houston G. Wood III, Ralph A. Lowry
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 325-334
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT83-A33256
ORIGEN2: A Versatile Computer Code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials
Allen G. Croff
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 335-352
Technical Paper | Analyses | doi.org/10.13182/NT83-1
U-Si and U-Si-Ai Dispersion Fuel Alloy Development for Research and Test Reactors
R. F. Domagala, T. C. Wiencek, H. R. Thresh
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 353-360
Technical Note | Nuclear Fuel | doi.org/10.13182/NT83-A33258
Analytic Solution to Verify Code Predictions of Two-Phase Flow in a Boiling Water Reactor Core Channel
Kuo-Fu Chen, C. A. Olson
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 361-363
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33259
A Mobile Gamma Scanning System for Detecting Radiation Anomalies
Tim E. Myrick, Michael S. Blair, Richard W. Doane, William A. Goldsmith
Nuclear Technology | Volume 62 | Number 3 | September 1983 | Pages 364-370
Technical Note | Technique | doi.org/10.13182/NT83-A33260
