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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Nuclear Science and Engineering
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Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
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Fault-Tree Analysis of Criticality in a Pulsed Column of a Typical Reprocessing Facility
Yasushi Nomura, Yoshitaka Naito
Nuclear Technology | Volume 121 | Number 1 | January 1998 | Pages 3-13
Technical Paper | Kiyose Birthday Anniversary | doi.org/10.13182/NT98-A2814
Study on the Permeability of Engineered Barriers for the Enhancement of a Radioactive Waste Repository System
Shingo Tashiro, Ai Fujiwara, Muneaki Senoo
Nuclear Technology | Volume 121 | Number 1 | January 1998 | Pages 14-23
Technical Paper | Kiyose Birthday Anniversary | doi.org/10.13182/NT98-A2815
Integrated Radionuclide Transport Model for a High-Level Waste Repository in Water-Saturated Geologic Formations
Joonhong Ahn
Nuclear Technology | Volume 121 | Number 1 | January 1998 | Pages 24-39
Technical Paper | Kiyose Birthday Anniversary | doi.org/10.13182/NT121-24
Stability of Natural Circulation Boiling Water Reactors: Part I - Description Stability Model and Theoretical Analysis in Terms of Dimensionless Groups
David D. B. van Bragt, Tim H. J. J. van der Hagen
Nuclear Technology | Volume 121 | Number 1 | January 1998 | Pages 40-51
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2817
Stability of Natural Circulation Boiling Water Reactors: Part II - Parametric Study of Coupled Neutronic-Thermohydraulic Stability
Nuclear Technology | Volume 121 | Number 1 | January 1998 | Pages 52-62
Technical Paper | Reactor Safety | doi.org/10.13182/NT98-A2818
Self-Diffusion of Sodium Ions in Compacted Sodium Montmorillonite
Tamotsu Kozaki, Atsushi Fujishima, Seichi Sato, Hiroshi Ohashi
Nuclear Technology | Volume 121 | Number 1 | January 1998 | Pages 63-69
Technical Paper | Criticality of Nuclear Materials | doi.org/10.13182/NT98-A2819
Probabilistic Model of Iodine Release for Steam Generator Tube Primary-to-Secondary Leakage Induced by Main Steam-Line Break
Peter S. Jackson, Patrick J. Williams
Nuclear Technology | Volume 121 | Number 1 | January 1998 | Pages 70-80
Technical Paper | Human Factors | doi.org/10.13182/NT98-A2820
Control of a Fast Reactor Cooled by Supercritical Light Water
Tohru Nakatsuka, Yoshiaki Oka, Seiichi Koshizuka
Nuclear Technology | Volume 121 | Number 1 | January 1998 | Pages 81-92
Technical Paper | Reactor Operations and Control | doi.org/10.13182/NT98-A2821
Fifteen Years of Research and Development on Direct Disposal in Germany: An Overview
Klaus-Detlef Closs, Reiner Papp
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 101-113
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2822
An Assessment of the Results of the Direct Disposal Project by the Federal Ministry for the Environment, Nature Conservation, and Nuclear Safety
Manfred Bloser, Thomas Beuth
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 114-119
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2823
Evaluation of Direct Disposal from the Point of View of One Utility and Perspectives for Waste Management
Wolfgang Heni
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 120-127
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2824
Status of the Gorleben Pilot Conditioning Plant
Hans-Otto Willax
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 128-135
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2825
Status of the Development of Final Disposal Casks and Prospects in Germany
Klaus Janberg, Harry Spilker
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 136-147
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2826
Conceptual Design and Demonstration Tests for Disposal of Spent Fuel in a Salt Repository
Hans-Jürgen Engelmann
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 148-161
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2827
International Nuclear Material Safeguards for the Direct Final Disposal of Spent-Fuel Assemblies
Bernd Richter
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 162-167
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2828
Retrievability of Spent Nuclear Fuel After Final Disposal in a Salt Dome
Enrique A. Biurrun
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 168-173
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2829
Long-Term Stability of Spent Nuclear Fuel Waste Packages in Gorleben Salt Repository Environments
Bernd Grambow, Andreas Loida, Emmanuel Smailos
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 174-188
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2830
Special Safety Aspects of Drift Disposal - The Thermal Simulation of the Drift Storage Experiment
Tilmann Rothfuchs, Johannes Droste, Hans-Karl Feddersen, Stefan Heusermann, Jörn U. Schneefuss, Alexandra Pudewills
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 189-198
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2831
Evaluation of Repository Concepts for the Disposal of Spent Fuel on the Basis of Geotechnical Safety Indicators and Exploration Data
Michael Langer, Manfred Wallner
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 199-211
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2832
A Comparison of Long-Term Safety Aspects - Concepts for Disposal of Spent Fuel and Wastes from Reprocessing
Richard Storck, Dieter Buhmann
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 212-220
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2833
Further Development Work for a Future Gorleben Repository
Jürgen P. Lempert
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 221-226
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2834
Overview of Electric Power Research Institute Nuclear Safety Analysis Activities
Lance J. Agee
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 229-236
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2835
Validation of the Laguna Verde RETRAN-03 Model for Pressurization Transients
Jorge Solis-Rodarte, Juan Carlos Ramos, Enrique Salaices
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 237-244
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2836
Simulation of a BWR-5 Plant: Verification and Validation of RETRAN-03
Michitsugu Mori
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 245-259
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2837
Benchmarking and Qualification of RETRAN-03 for BWR Stability Analysis by Comparison with Frequency-Domain Stability Analysis Code
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 260-274
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2838
Cofrentes Reload Licensing Methodology with RETRAN-03
Pedro Mata, Rafael de la Fuente, Pablo G. Sedano, Juan Serra
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 275-288
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2839
TU Electric's Experiences with the Development and NRC Approval of a Reload Safety Analysis Methodology
W. James Boatwright, David W. Hiltbrand, Whee G. Choe
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 289-294
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2840
Steam Generator Tube Plugging and Replacement Analyses for McGuire and Catawba
Gregg B. Swindlehurst
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 295-301
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2841
Plant-Specific RETRAN Analyses in Support of Chinshan BWR/4 Operation
Jan-Ru Tang, Lainsu Kao, Der-Yeong Shiau, Lin-Yao Chou, Ching-Chuan Yao, Show-Chyuan Chiang
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 302-312
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2842
Calculation of BWR Shroud Head Loads and Axial Lift During a Main Steam-Line Break
John M. Sorensen, Nicholas G. Trikouros
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 313-323
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2843
Thermal-Hydraulic Analysis of Core Shroud Crack for Chinshan BWR/4 Unit 2 Using RETRAN-02/MOD5
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 324-336
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2844
Detectability of BWR Core Shroud Separation Through Anomalous Core Characteristics
Hiroshi Kawai, Ichio Tomiai
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 337-345
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2845
Realistic Scoping Study of Reactivity Insertion Accidents for Typical PWR and BWR Cores
Antonio F. Dias, Laurance D. Eisenhart, Ronald E. Engel, Lance J. Agee
Nuclear Technology | Volume 121 | Number 3 | March 1998 | Pages 346-358
Technical Paper | RETRAN | doi.org/10.13182/NT98-A2846
