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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
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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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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Test Results of Ya-21u Thermionic Space Power System
Dmitry V. Paramonov, Mohamed S. El-Genk
Nuclear Technology | Volume 117 | Number 1 | January 1997 | Pages 1-14
Technical Paper | Fission Reactor | doi.org/10.13182/NT97-A35332
Gross Xenon Stability
Jeffery D. Lewins, Paul P. H. Wilson
Nuclear Technology | Volume 117 | Number 1 | January 1997 | Pages 15-39
Technical Paper | Fission Reactor | doi.org/10.13182/NT97-A35333
How the Code Analyst Can Influence the Calculation and Use Good Practices to Minimize Pitfalls
Louis M. Shotkin
Nuclear Technology | Volume 117 | Number 1 | January 1997 | Pages 40-48
Technical Paper | Fission Reactor | doi.org/10.13182/NT97-A35334
An Assessment of Ex-Vessel Fuel/Coolant Interaction Energetics for Advanced Light Water Reactors
John G. Murphy, Michael L. Corradini
Nuclear Technology | Volume 117 | Number 1 | January 1997 | Pages 49-63
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35335
The Safety Concerns of Spent-Fuel Pool Reracking in Taiwan’s Maanshan Nuclear Power Station
Hsin-Ho Lee
Nuclear Technology | Volume 117 | Number 1 | January 1997 | Pages 64-79
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35336
Investigations on the Partitioning of 129I from Silver-Impregnated Silica in Preparation for Future Transmutation
Giuseppe Modolo, Reinhard Odoj
Nuclear Technology | Volume 117 | Number 1 | January 1997 | Pages 80-86
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35337
A Computational Model for Thermal Fluid Design Analysis of Nuclear Thermal Rockets
Jeff A. Given, Samim Anghaie
Nuclear Technology | Volume 117 | Number 1 | January 1997 | Pages 87-108
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35338
Posttest Calculations of Bundle Quench Test CORA-13 with ATHLET-CD
Josef Bestele, Klaus Trambauer, Johann-Dietrich Schubert
Nuclear Technology | Volume 117 | Number 1 | January 1997 | Pages 109-123
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35339
A Pressurized Water Reactor Design for Plutonium Incineration: Fuel Cycle Options
Alex Galperin, Gilad Raizes
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 125-132
Technical Paper | Fission Reactor | doi.org/10.13182/NT97-A35319
Parallel and Serial Applications of the RETRAN-03 Power Plant Simulation Code Using Domain Decomposition and Krylov Subspace Methods
Thomas J. Downar, Jen-Ying Wu, John Steill, Raghunandan Janardhan
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 133-150
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35320
Mechanical Efficiency of the Energy Release During a Steam Explosion
R. Krieg
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 151-157
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35321
Material Distribution in Light Water Reactor-Type Bundles Tested Under Severe Accident Conditions
Volker Noack, Siegfried J. L. Hagen, Peter Hofmann, Gerhard Schanz, Leo K. Sepold
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 158-170
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35322
Transuranium Fuel Assembly for Transmutation in a Pressurized Water Reactor
Masaaki Mori, Mitsuru Kawamura, Akio Yamamoto
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 171-183
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35323
Boiling Water Reactor Benchmark Calculations
Farzad Rahnema, Dan Ilas, Shivakumar Sitaraman
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 184-194
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35324
Melting Tests for Recycling Slightly Radioactive Metallic Wastes Arising from Decommissioning
Hisashi Nakamura, Kazuo Fujiki
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 195-205
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35325
Evaluation of Shielding Analysis Methods in Spent-Fuel Cask Environments
Bryan L. Broadhead, Jabo S. Tang, Robert L. Childs, Cecil V. Parks, Hiroaki Taniuchi
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 206-222
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT97-A35326
Radionuclide Transport in Fractured Porous Media—Analytical Solutions for a System of Parallel Fractures with a Flux-Type Boundary Condition
Chu-Tien Chen, Shih-Hai Li
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 223-233
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT97-A35327
Evaluation of Subcooled Critical Heat Flux Correlations Using the PU-BTPFL CHF Database for Vertical Upflow of Water in a Uniformly Heated Round Tube
David D. Hall, Issam Mudawar
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 234-247
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35328
Criticality Safety Assessment of a TRIGA Reactor Spent-Fuel Pool Under Accident Conditions
Bogdan Glumac, Matjaž Ravnik, Marjan Logar
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 248-254
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT97-A35329
Virtual Radiation Fields—A Virtual Environment Tool for Radiological Analysis and Simulation
Travis W. Knight, G. Ronald Dalton, James S. Tulenko
Nuclear Technology | Volume 117 | Number 2 | February 1997 | Pages 255-266
Technical Paper | Radiation Protection | doi.org/10.13182/NT97-A35330
Improvement and Assessment of the CATHARE 2 Three-Dimensional Module Compared with the UPTF Downcomer Test 7
Jae-Jun Jeong, Isabelle Dor, Dominique Bestion
Nuclear Technology | Volume 117 | Number 3 | March 1997 | Pages 267-280
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35341
Development of a Three-Dimensional Core Dynamics Analysis Program for Commercial Boiling Water Reactors
Yasunori Bessho, Yuichiro Yoshimoto, Osamu Yokomizo, Ryutaro Yamashita, Masumi Ishikawa, Akio Toba
Nuclear Technology | Volume 117 | Number 3 | March 1997 | Pages 281-292
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT97-A35342
Transmutation of Technetium and Iodine—Irradiation Tests in the Frame of the EFTTRA Cooperation
Rudy J. M. Konings, Wout M. P. Franken, Rainer P. Conrad, Jean-Francois Gueugnon, Jean-Claude Spirlet
Nuclear Technology | Volume 117 | Number 3 | March 1997 | Pages 293-298
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35343
Studies on the Restructuring of Fast Breeder Test Reactor Fuel by Out-of-Pile Simulation
M. P. Antony, J. Daniel, C. K. Mathews
Nuclear Technology | Volume 117 | Number 3 | March 1997 | Pages 299-305
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35344
Local Analysis Technique for the Advanced Neutron Source Reactor Fuel Defect Studies
Gary E. Giles, Jr.
Nuclear Technology | Volume 117 | Number 3 | March 1997 | Pages 306-315
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT97-A35345
Transport of Weapons-Grade Plutonium and Boron Through Fractured Geologic Media
Joonhong Ahn
Nuclear Technology | Volume 117 | Number 3 | March 1997 | Pages 316-328
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT97-A35346
Development of an Integrated Transuranic Waste Management System for a Large Research Facility: NUCEF
Hideaki Mineo, Tatsuro Matsumura, Isao Takeshita, Ichio Nishizawa, Susumu Sugikawa, Takeshi Tsujino
Nuclear Technology | Volume 117 | Number 3 | March 1997 | Pages 329-339
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT97-A35347
Estimation of Anisotropic Factor and Turbulent Mixing Rate in Rod Bundles Based on the Flow Pulsation Phenomenon
Sin Kim, Goon-Cherl Park
Nuclear Technology | Volume 117 | Number 3 | March 1997 | Pages 340-352
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35348
Moisture Fraction Measurements for Two-Phase Mist Flow Using High-Sensitivity Capacitance Sensors
Michael F. Dowling, Jason D. Wartell, Sheldon M. Jeter, Said I. Abdel-Khalik
Nuclear Technology | Volume 117 | Number 3 | March 1997 | Pages 353-365
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT97-A35349
