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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
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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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Investigation of Failed Fuel Detection and Location Using a Flux Tilting Method in a Fast Breeder Reactor
Masao Hamada, Kunio Uehara, Kazuyoshi Muramatsu, Takanobu Kamei, Tetsuo Tamaoki, Mitsuaki Yamaoka, † Yukio Sonoda, Yuji Sano, Masuo Sato, Takayuki Sudo
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 1-13
Technical Paper | Fast Reactor Safety / Fission Reactor | doi.org/10.13182/NT92-A34646
Study of Thermal-Hydraulic Characteristics During Decay Heat Removal in a Pool-Type Fast Breeder Reactor
Masayoshi Akutsu, Yoshinobu Okabe, Kazuziro Satoh, Hideki Kamide, Kenji Hayashi, Nobuyuki Naohara, Kengo Iwashige, Yoji Shibata
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 14-26
Technical Paper | Fast Reactor Safety / Fission Reactor | doi.org/10.13182/NT92-A34647
Investigations of Sloshing Fluid Motions in Pools Related to Recriticalities in Liquid-Metal Fast Breeder Reactor Core Meltdown Accidents
Werner Maschek, Claus Dieter Munz, Leonhard Meyer
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 27-43
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34648
Modeling Transient Fission Gas Behavior for Solid, Melting, and Molten Fuel in the Computer Program LAKU
L. Väth
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 44-53
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34649
Improvement of Evaluation Method for Initiating-Phase Energetics Based on CABRI-1 In-Pile Experiments
Nobuyuki Nonaka, Ikken Sato
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 54-69
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34650
Molten Fuel Propagation in Sodium-Filled Fast Reactor Subassembly Geometries
Allen J. Edwards, M. J. Bird, Michael K. Denham
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 70-78
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34651
Pouring of 100-kg-Scale Molten UO2 into Sodium
Daniel Magallon, Hermann Hohmann, Hubert Schins
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 79-90
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34652
Fuel Motion in Overpower Tests of Metallic Integral Fast Reactor Fuel
Edgar A. Rhodes, Theodore H. Bauer, George S. Stanford, James P. Regis, Charles E. Dickerman
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 91-99
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34653
A Model for an Effective Equation of State of Irradiated Fast Reactor Fuel
Erhard A. Fischer
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 100-112
Technical Paper | Fast Reactor Safety / Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34654
Sinusoidal Source Perturbation Experiments with a Breached Fuel Subassembly in the Experimental Breeder Reactor II
Kenny C. Gross, Robert V. Strain
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 113-123
Technical Paper | Fast Reactor Safety / Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34655
Features of Postfailure Fuel Behavior in Transient Overpower and Transient Undercooled/Overpower Tests in the Transient Reactor Test Facility
Robert C. Doerner, Theodore H. Bauer, James A. Morman, John W. Holland
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 124-136
Technical Paper | Fast Reactor Safety / Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34656
Robust Optimal Control of Nuclear Reactors and Power Plants
Robert M. Edwards, Kwang Y. Lee, Asok Ray
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 137-148
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34669
DF-4 Analysis Using SCDAP/RELAP5
Judith K. Hohorst, Chris M. Allison
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 149-159
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34670
Sensitivity, Uncertainty, and Importance Analysis of a Risk Assessment
Risto S. Andsten, Jussi K. Vaurio
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 160-170
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34671
Failure Probability of Axially Cracked Steam Generator Tubes: A Probabilistic Fracture Mechanics Model
Borut Mavko, Leon Cizelj
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 171-177
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34672
Crud Formation by Palladium Particles as Insoluble Residues
Kenzo Munakata, Hiroshi Sugai, Shigehiko Miyachi, Shouzo Yasu
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 178-187
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT92-A34673
Emulsions Stabilized by Precipitates of Zirconium and Tributyl Phosphate Degradation Products
Hiroshi Sugai, Kenzo Munakata, Shigehiko Miyachi, Shouzo Yasu
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 188-195
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT92-A34674
Estimate of the Crud Contribution to Shipping Cask Containment Requirements
Robert P. Sandoval, Robert E. Einziger, Hans Jordan, Anthony P. Malinauskas, Walter J. Mings
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 196-206
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT92-A34675
Analysis of Palladium Coatings to Remove Hydrogen Isotopes from Zirconium Fuel Rods in Canada Deuterium Uranium-Pressurized Heavy Water Reactors: Thermal and Neutron Diffusion Effects
Cynthia L. Stokes, Robert E. Buxbaum
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 207-216
Technical Paper | Material | doi.org/10.13182/NT92-A34676
Neutron Autoradiography of Trace Amounts of Gadolinium
Jing-Luen A. Shih, Robert M. Brugger†
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 217-223
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT92-A34677
An Analysis for the Failed Steam Generator Tube Plug
Hsu-Chieh Yeh, Robert F. Keating, R. Michael Roidt, L. E. Hochreiter
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 224-229
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34678
Semi-Markov Reliability Analysis of Alternating Systems in a Nuclear Power Plant
Kwang Nam Lee, Nam Zin Cho
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 230-241
Technical Paper | Reactor Operation | doi.org/10.13182/NT92-A34679
Electrochemical Decontamination of Metallic Surfaces Contaminated by Spent-Fuel Storage Pool Water
Prakash B. Chaudhary, Manohar G. Bhide
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 242-244
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34680
Consequences of Instability and Nonstoichiometry in High-Temperature Nuclear Fuels
Donald G. Schweitzer
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 245-252
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34681
The Reactor Physics Design of Gas-Cooled Cermet Reactors and Their Potential Application to Space Power Systems
S. N. Jahshan
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 257-276
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34658
Accident Management for a Loss of Feedwater in a Pressurized Water Reactor
Carmelo Billa, Francesco D’Auria, Giorgio Maria Galassi
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 277-288
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34659
An Analysis of Feed-and-Bleed Cooling of a Pressurized Water Reactor
Min Lee, Jiing-Huae Wu
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 289-306
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34660
A Prototype Expert System for the Monitoring of Defected Nuclear Fuel Elements in Canada Deuterium Uranium Reactors
Brent J. Lewis, Russell J. Green, Christopher W. T. Che
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 307-321
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34661
An Epithermal Neutron Beam for Neutron Capture Therapy at the Missouri University Research Reactor
Robert M. Brugger, Jing-Luen A. Shih, Hungyuan B. Liu
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 322-332
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT92-A34662
Validation and Extension of a Correlation for Predicting Onset of Nucleate Boiling in Plate-Type Research Reactors
Efigenio Cubillos-Moreno, Mohamed Belhadj, Tunc Aldemir
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 333-348
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34663
Elementary Model to Predict the Pressure Loss Across a Spacer Grid Without a Mixing Vane
Nae-Hyun Kim, Sang Keun Lee, Kap Suk Moon
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 349-353
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34664
Bundle Critical Power Predictions Under Normal and Abnormal Conditions in Pressurized Water Reactors
Wen-Shan Lin, Bau-Shei Pei, Chien-Hsiung Lee
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 354-365
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34665
Application of Generation and Condensation Models to Predict Subcooled Boiling Void at Low Pressures
VIjay Chatoorgoon, Geoffrey R. Dimmick, Michael B. Carver, William N. Selander, Mamdouh Shoukri
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 366-378
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34666
Measurements of Gamma-Ray Shielding Properties of Ilmenite-Magnetite Concrete and Polyboron Slabs Using a 252Cf Source
F. U. Ahmed, S. I. Bhuiyan, A. S. Mollah, M. M. Rahman
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 379-386
Technical Note | Radiation Protection | doi.org/10.13182/NT92-A34667
