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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.
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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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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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Monte Carlo Simulation of the Massachusetts Institute of Technology Research Reactor
Everett L. Redmond II, Jacquelyn C. Yanch, Otto K. Harling
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 1-14
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A34946
Assessment of the Impact of Neutronic/Thermal-Hydraulic Coupling on the Design and Performance of Nuclear Reactors for Space Propulsion
Shashikant M. Aithal, Tunc Aldemir, Kambiz Vafai
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 15-30
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A34947
Conceptual Design Station Blackout and Loss-of-Flow Accident Analyses for the Advanced Neutron Source Reactor
C. D. Fletcher, L. S. Ghan, J. C. Determan, H. H. Nielsen
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 31-45
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34948
Simultaneous Bottom and Top-Down Rewetting Calculations with the CATHARE Code
Jan Bartak, Timo Haapalehto
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 46-59
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34949
Mixed-Oxide Fuel Fabrication Technology and Experience at the Belgonucléaire and CFCa Plants and Further Developments for the MELOX Plant
Didier Haas, Alain Vandergheynst, Jean van Vliet, Robert Lorenzelli, Jean-Louis Nigon
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 60-82
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A34950
A Two-Dimensional Finite Element Method Large Eddy Simulation for Application to Turbulent Steam Generator Flow
Freddie J. Davis, Jr., Yassin A. Hassan
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 83-99
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34951
Visualization of the Lower Plenum Anomaly in the Westinghouse AP600 Reactor
Thomas D. Radcliff, William S. Johnson, J. Roger Parsons, Douglas E. Ekeroth
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 100-109
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34952
Development of In-Service Inspection Priorities for Pressurized Water Reactor High-Pressure Injection System Components
Truong V. Vo, Doyle R. Edwards
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 110-124
Technical Paper | Reactor Operation | doi.org/10.13182/NT94-A34953
Development of the Kuosheng Plant Analyzer and Its Assessment with Plant Data
Shih-Jen Wang, Chun-Sheng Chien, Chia-Yu Wang, Tsu-Chi Lyie, Shih-Hsiin Chang, Der-Chyuan Wang, Suh-Chyn Jeng
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 125-134
Technical Note | Fission Reactor | doi.org/10.13182/NT94-A34954
The Scaling Parameter of the Sigmoid Function in Artificial Neural Networks
Tim H. J. J. van der Hagen
Nuclear Technology | Volume 106 | Number 1 | April 1994 | Pages 135-138
Technical Note | Reactor Control | doi.org/10.13182/NT94-A34955
Evaluation of a Severe Accident Management Strategy for Boiling Water Reactors—Drywell Flooding
Donghan Yu, Leiming Xing, William E. Kastenberg, David Okrent
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 139-154
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34971
Mean Importance Measures for Groups of Events in Fault Trees
F. Eric Haskin, Min Huang, M. Kent Sasser, Desmond W. Stack
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 155-167
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34972
Analysis of the Chemical Behavior of Iodine in the Suppression Tank of the LOFT Facility During Experiment LP-FP-2 with IODE and IMPAIR-2/M
Luis E. Herranz, Jesús Polo
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 168-176
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34973
Interaction of Nickel Ions with Magnetite Particles in High-Temperature Water
Kostadin A. Dinov, Kenkichi Ishigure, Daisuke Hiroishi, Chihiro Matsuura
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 177-185
Technical Paper | Material | doi.org/10.13182/NT94-A34974
Modeling of Bubbly and Annular Two-Phase Flow in Subchannel Geometries with BACCHUS-3D/TP
Maurizio Bottoni, Robert W. Lyczkowski
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 186-201
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34975
Theoretical Modeling of Forced Convection Condensation of Steam in a Vertical Tube in the Presence of a Noncondensable Gas
Mansoor Siddique, Michael W. Golay, Mujid S. Kazimi
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 202-215
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34976
Optimal Reliable Control System Design for Steam Generators in Pressurized Water Reactors
Wencheng Wu, Chaung Lin
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 216-224
Technical Paper | Reactor Control | doi.org/10.13182/NT94-A34977
Accelerating Learning of Neural Networks with Conjugate Gradients for Nuclear Power Plant Applications
Jaques Reifman, Javier E. Vitela
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 225-241
Technical Paper | Reactor Control | doi.org/10.13182/NT94-A34978
Fuzzy Power Control Algorithm for a Pressurized Water Reactor
Yung-Joon Hah, Byong-Whi Lee
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 242-253
Technical Paper | Reactor Control | doi.org/10.13182/NT94-A34979
Low-Power Experimental Study of the Demand Surface for Annular Geometry Fuel Elements with Upflow of Coolant
Allen C. Smith, James E. Blake, Michael T. Childerson, Ted R. Ohrn, Robert M. Privette
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 254-260
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34980
Film Dosimeters Based on Methylene Blue and Methyl Orange in Polyvinyl Alcohol
Woon Hyuk Chung, Arne Miller
Nuclear Technology | Volume 106 | Number 2 | May 1994 | Pages 261-264
Technical Note | Radiation Protection | doi.org/10.13182/NT94-A34981
A Study of Plateout Fission Product Behavior During a Large-Scale Pipe Rupture Accident in a High-Temperature Gas-Cooled Reactor
Kazuhiro Sawa, Isao Murata, Shusaku Shiozawa, Mikio Matsumoto
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 265-273
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34957
Modeling of Heat Transfer to Nuclear Steam Supply System Heat Sinks and Application to Severe Accident Sequences
Kune Y. Suh
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 274-291
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34958
Xenon Stability Analysis Using the Generalized Nyquist Criterion
You-Cho Choi, Goon-Cherl Park, Chang-Hyun Chung
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 292-299
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34959
A Study on Boiling Water Reactor Regional Stability from the Viewpoint of Higher Harmonics
Yutaka Takeuchi, Yukio Takigawa, Hitoshi Uematsu
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 300-314
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34960
Use of an Influence Diagram and Fuzzy Probability for Evaluating Accident Management in a Boiling Water Reactor
Donghan Yu, William E. Kastenberg, David Okrent
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 315-325
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34961
Trace Metal Assay of Uranium Silicide Fuel
M. J. Kulkarni, A. A. Argekar, S. K. Thulasidas, B. A. Dhawale, B. Rajeswari, V. C. Adya, P. J. Purohit, G. Neelam, T. R. Bangia, A. G. Page, M. D. Sastry, R. H. Iyer
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 326-333
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A34962
Numerical Analysis for Microstructure Change of a Light Water Reactor Fuel Pellet at High Burnup
Takanori Kameyama, Tetsuo Matsumura, Motoyasu Kinoshita
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 334-341
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A34963
Internal Flaws in the Silicon Carbide Coating of Fuel Particles for High-Temperature Gas-Cooled Reactors
Kazuo Minato, Hironobu Kikuchi, Kousaku Fukuda, Nobuyuki Suzuki, Hiroshi Tomimoto, Nobu Kitamura, Mitsunobu Kaneko
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 342-349
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A34964
An Evaluation of the Deployment of AIROX-Recycled Fuel in Pressurized Water Reactors
Salim N. Jahshan, Thomas J. McGeehan
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 350-359
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT94-A34965
Transport Phenomena and Occupational Consequences of a Tritium Release
Dong H. Nguyen
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 360-372
Technical Paper | Radiation Protection | doi.org/10.13182/NT94-A34966
Measurement of Neutron Radiation Exposure of Commercial Airline Pilots Using Bubble Detectors
Brent J. Lewis, Richard Kosierb, Tom Cousins, Donald F. Hudson, Georges Guéry
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 373-383
Technical Paper | Radiation Protection | doi.org/10.13182/NT94-A34967
Development of Software for the Microsimulator for the KO-RI Nuclear Power Plant Unit 2
Ho Seok, Hee Cheon No, Sung Jae Cho, Sang Doug Park, Hwang Young Jun, Yong Kwan Lee
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 384-396
Technical Paper | Reactor Operation | doi.org/10.13182/NT94-A34968
Verification of Feedwater System Models of the Kuosheng Plant Analyzer
Shih-Jen Wang, Chun-Sheng Chien, Shih-Hsiin Chang, Suh-Chyn Jeng
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 397-406
Technical Paper | Reactor Control | doi.org/10.13182/NT94-A34969
