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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!
Latest Magazine Issues
Feb 2025
Jul 2024
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Nuclear Science and Engineering
March 2025
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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Progress of the DUPIC Fuel Compatibility Analysis - IV: Fuel Performance
Hangbok Choi, Ho Jin Ryu, Gyuhong Roh, Chang Joon Jeong, Chang Je Park, Kee Chan Song, Jung Won Lee, Myung Seung Yang
Nuclear Technology | Volume 157 | Number 1 | January 2007 | Pages 1-17
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3798
Comparative Transient Analysis of Critical and Subcritical 80-MW Pb-Bi Eutectic-Cooled Reactor Systems
K. Mikityuk, P. Coddington, S. Pelloni, E. Bubelis, R. Chawla
Nuclear Technology | Volume 157 | Number 1 | January 2007 | Pages 18-36
Technical Paper | Reactor Safety | doi.org/10.13182/NT07-A3799
Zirconium Matrix Cermet for a Mixed Uranium-Thorium Oxide Fuel in an SBWR
Sean M. McDeavitt, Yunlin Xu, Thomas J. Downar, Alvin A. Solomon
Nuclear Technology | Volume 157 | Number 1 | January 2007 | Pages 37-52
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3800
Improvement of Fuel Performance Code COSMOS with Recent In-Pile Data for MOX and UO2 Fuels
Byung-Ho Lee, Yang-Hyun Koo, Je-Yong Oh, Jin-Sik Cheon, Dong-Seong Sohn
Nuclear Technology | Volume 157 | Number 1 | January 2007 | Pages 53-64
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3801
Integrator Circuit as an Analogy for Convection
S. Usman, S. Abdallah, M. Hawwari, M. Scarangella, L. Shoaib
Nuclear Technology | Volume 157 | Number 1 | January 2007 | Pages 65-73
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3802
Water Adsorption Isotherms for Charged and Uncharged Cesium Iodide Aerosol Particles
Charles A. Riggs, Robert V. Tompson, Tushar K. Ghosh, Sudarshan K. Loyalka, Dabir S. Viswanath
Nuclear Technology | Volume 157 | Number 1 | January 2007 | Pages 74-86
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT07-A3803
Environmental Impact of Yucca Mountain Repository in the Case of Canister Failure
Joonhong Ahn
Nuclear Technology | Volume 157 | Number 1 | January 2007 | Pages 87-105
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT07-A3804
Dead-Time Correction for Nonparalyzing Detectors When Measuring Short-Lived Nuclides
Andrija S. Radovic, Shoaib Usman
Nuclear Technology | Volume 157 | Number 1 | January 2007 | Pages 106-109
Technical Paper | Radiation Measurements and Instrumentation | doi.org/10.13182/NT07-A3805
Research and Development on System Integration Technology for Connection of Hydrogen Production System to an HTGR
Yoshiyuki Inagaki, Hirofumi Ohashi, Yoshitomo Inaba, Hiroyuki Sato, Tetsuo Nishihara, Tetsuaki Takeda, Koji Hayashi, Masuro Ogawa
Nuclear Technology | Volume 157 | Number 2 | February 2007 | Pages 111-119
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3806
A Compact Loop-Type Fast Reactor Without Refueling for a Remote Area Power Source
Yoshitaka Chikazawa, Yasushi Okano, Mamoru Konomura, Naoki Sawa, Yoshio Shimakawa, Toshihiko Tanaka
Nuclear Technology | Volume 157 | Number 2 | February 2007 | Pages 120-131
Technical Paper | Fission Reactors | doi.org/10.13182/NT07-A3807
Benchmark Study on Fuel Bundle Degradation in the Phebus FPT3 Test Using the Severe Accident Codes ATHLET-CD, ICARE2, and MELCOR
Bela Toth, Klaus Mueller, Jon Birchley, Hozumi Wada, Claude Jamond, Klaus Trambauer
Nuclear Technology | Volume 157 | Number 2 | February 2007 | Pages 132-142
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3808
Proliferation Resistance Assessment Methodology for Nuclear Fuel Cycles
William S. Charlton, Ryan F. LeBouf, Claudio Gariazzo, D. Grant Ford, Carl Beard, Sheldon Landsberger, Michael Whitaker
Nuclear Technology | Volume 157 | Number 2 | February 2007 | Pages 143-156
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3809
Fertile-Free Fuels in Pressurized Water Reactors: Design Challenges and Solutions
E. Fridman, E. Shwageraus, A. Galperin
Nuclear Technology | Volume 157 | Number 2 | February 2007 | Pages 157-176
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3810
Validation of Coupled Thermal-Hydraulic and Neutronics Codes for Safety Analysis by International Cooperations
Kostadin Ivanov, Enrico Sartori, E. Royer, S. Langenbuch, K. Velkov
Nuclear Technology | Volume 157 | Number 2 | February 2007 | Pages 177-195
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3811
Head Loss Characteristics of a Fibrous Bed in a PWR Chemical Environment
Ashok K. Ghosh, Kerry J. Howe, Arup K. Maji, Bruce C. Letellier, Russell C. Jones
Nuclear Technology | Volume 157 | Number 2 | February 2007 | Pages 196-207
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3812
Theoretical Analysis of the Working Performance of the Hydraulic Control Rod Driving System in Perturbation or Inclination
Yanhua Zheng, Hanliang Bo, Duo Dong
Nuclear Technology | Volume 157 | Number 2 | February 2007 | Pages 208-214
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT07-A3813
The PROMETRA Program: Fuel Cladding Mechanical Behavior Under High Strain Rate
B. Cazalis, J. Desquines, C. Poussard, M. Petit, Y. Monerie, C. Bernaudat, P. Yvon, X. Averty
Nuclear Technology | Volume 157 | Number 3 | March 2007 | Pages 215-229
Technical Paper | Reactivity-Initiated Accident (RIA) | doi.org/10.13182/NT07-A3814
Summary and Interpretation of the CABRI REP-Na Program
J. Papin, B. Cazalis, J. M. Frizonnet, J. Desquines, F. Lemoine, V. Georgenthum, F. Lamare, M. Petit
Nuclear Technology | Volume 157 | Number 3 | March 2007 | Pages 230-250
Technical Paper | Reactivity-Initiated Accident (RIA) | doi.org/10.13182/NT07-A3815
Boiling Water Reactor Fuel Lattice Enrichment Distribution Optimization Using Tabu Search and Fuzzy Logic
Cecilia Martin-del-Campo, Juan Luis François, Alejandra M. Barragan, Miguel A. Palomera
Nuclear Technology | Volume 157 | Number 3 | March 2007 | Pages 251-260
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3816
Azimuthal Film-Boiling Heat Transfer from a Downward-Facing Hemisphere
Mong J. Yu, Chan S. Kim, Kune Y. Suh
Nuclear Technology | Volume 157 | Number 3 | March 2007 | Pages 261-276
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3817
Studies of an Accelerator-Driven Transuranium Burner with Hafnium-Based Inert Matrix Fuel
Kamil Tucek, Mikael Jolkkonen, Janne Wallenius, Waclaw Gudowski
Nuclear Technology | Volume 157 | Number 3 | March 2007 | Pages 277-298
Technical Paper | Accelerators | doi.org/10.13182/NT07-A3818
Performance of Advanced Self-Shielding Models in DRAGON for the Estimation of CANDU-6 Safety Parameters
Ramamoorthy Karthikeyan, Alain Hébert
Nuclear Technology | Volume 157 | Number 3 | March 2007 | Pages 299-316
Technical Note | Fission Reactors | doi.org/10.13182/NT07-A3819
