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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!
Latest Magazine Issues
Feb 2025
Jul 2024
Latest Journal Issues
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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Beyond-Design-Basis-Accidents Passive Containment-Cooling Spray System
Aly Karameldin, Hassan M. Elsawy Temraz, Nady Attia Ibrahim
Nuclear Technology | Volume 136 | Number 1 | October 2001 | Pages 1-13
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3224
Development of a Fast Breeder Reactor Fuel Bundle-Duct Interaction Analysis Code - BAMBOO: Analysis Model and Validation by the Out-of-Pile Compression Test
Tomoyuki Uwaba, Kosuke Tanaka
Nuclear Technology | Volume 136 | Number 1 | October 2001 | Pages 14-23
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3225
Monitors for the Prediction of Alternate Nuclear Material Concentrations for Pressurized Water Reactor Spent Fuel
William S. Charlton, William D. Stanbro
Nuclear Technology | Volume 136 | Number 1 | October 2001 | Pages 24-36
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3226
Assessment and Application of the ROSE Code for Reactor Outage Thermal-Hydraulic and Safety Analysis
Thomas K. S. Liang, Fu-Kuang Ko, Liang-Che Dai
Nuclear Technology | Volume 136 | Number 1 | October 2001 | Pages 37-49
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3227
Realistic Small- and Intermediate-Break Loss-of-Coolant Accident Analysis Using WCOBRA/TRAC
Stephen M. Bajorek, Nikolay Petkov, Katsuhiro Ohkawa, Robert M. Kemper, Arthur P. Ginsberg
Nuclear Technology | Volume 136 | Number 1 | October 2001 | Pages 50-62
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3228
The Shielding Effect of Iron Louvers for Neutrons and Gamma Rays
Keigo Mio, Tetsuo Kurashige, Toshiso Kosako
Nuclear Technology | Volume 136 | Number 1 | October 2001 | Pages 63-75
Technical Paper | Radiation Protection | doi.org/10.13182/NT01-A3229
Induced Radioactivity and Waste Classification of Reactor Zone Components of the Chernobyl Nuclear Power Plant Unit 1 After Final Shutdown
Boris K. Bylkin, Galina B. Davydova, Yuri A. Zverkov, Alexander V. Krayushkin, Yuri A. Neretin, Anatoly V. Nosovsky, Valery A. Seyda, Steven M. Short
Nuclear Technology | Volume 136 | Number 1 | October 2001 | Pages 76-88
Technical Paper | Decontamination/Decommissioning | doi.org/10.13182/NT01-A3230
Development of the Process for the Recovery and Conversion of 233UF6 Chemisorbed in NaF Traps from the Molten Salt Reactor Remediation Project
Guillermo D. Del Cul, Alan S. Icenhour, Darrell W. Simmons
Nuclear Technology | Volume 136 | Number 1 | October 2001 | Pages 89-98
Technical Paper | Decontamination/Decommissioning | doi.org/10.13182/NT01-A3231
Unfavorable Conditions for Nuclear Criticality Following Disposal of Transuranic Waste at the Waste Isolation Pilot Plant
Rob P. Rechard, Lawrence C. Sanchez, Holly R. Trellue, Christine T. Stockman
Nuclear Technology | Volume 136 | Number 1 | October 2001 | Pages 99-129
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-3
A Critical Review of the Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent-Fuel Pool Storage
J. C. Wagner, C. V. Parks
Nuclear Technology | Volume 136 | Number 1 | October 2001 | Pages 130-140
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-A3233
Studies on the Comprehensive Methodology for Structuring Accident Mitigation Systems for Next-Generation Pressurized Water Reactors
Yonezo Tsujikura
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 141-157
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3234
A Statistical Approach to Predict the Failure Enthalpy and Reliability of Irradiated PWR Fuel Rods During Reactivity-Initiated Accidents
Cheol Nam, Yong-Hwan Jeong, Youn-Ho Jung
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 158-168
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3235
An Integral Response Scaling Method for Reduced-Height Test Facilities and Its Validation Using RELAP5 for Loss of RHR During Midloop Operation
Hyoung Tae Kim, Hee Cheon No
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 169-185
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3236
Thermal-Hydraulic Simulation of Localized Flow Characteristics in a Steam Generator
Yuh-Ming Ferng, Yin-Pang Ma, Jer-Cherng Kang
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 186-196
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3237
A New Method to Determine the Neutron Sensitivity of a Micro Fission Chamber for a Boiling Water Reactor
Atsushi Kimura, Kaoru Fujita, Masaharu Nakazawa, Shinya Fujita, Eiji Seki, Yutaka Tanaka, Shigehiro Kono
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 197-203
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3238
Safety Evaluation of Primary-Side Bleed-and-Feed Scenarios by an Experimental Loss of Feedwater Event at the IIST Facility
Tay-Jian Liu, Show-Chyuan Chiang
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 204-220
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3239
Incipient Fault Detection and Isolation of Field Devices in Nuclear Power Systems Using Principal Component Analysis
Nitin Kaistha, Belle R. Upadhyaya]
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 221-230
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT01-A3240
Radiolysis of Bicarbonate and Carbonate Aqueous Solutions: Product Analysis and Simulation of Radiolytic Processes
Zhongli Cai, Xifeng Li, Yosuke Katsumura, Osamu Urabe
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 231-240
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-A3241
Void Fraction Measurement in Subcooled-Boiling Flow Using High-Frame-Rate Neutron Radiography
Masatoshi Kureta, Hajime Akimoto, Takashi Hibiki, Kaichiro Mishima
Nuclear Technology | Volume 136 | Number 2 | November 2001 | Pages 241-254
Technical Paper | Radioisotopes | doi.org/10.13182/NT01-A3242
Coupling Model: A Common-Cause-Failure Model with Consideration of Interpretation Uncertainties
Albert Kreuser, Jörg Peschke
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 255-260
Technical Paper | Reactor Safety | doi.org/10.13182/NT01-A3243
Preliminary FRAPCON-3Th Steady-State Fuel Analysis of ThO2 and UO2 Fuel Mixtures
Eric P. Loewen, Rodrick D. Wilson, Judith K. Hohorst, Arvind S. Kumar
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 261-277
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3244
BWR Reload Strategy Based on Fixing Once-Burnt Fuel Between Cycles
Elizebeth M. Maag, Dave Knott
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 278-291
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-A3245
Development and Application of the Reactor Coolant On-Line Leakage Evaluation Model for Pressurized Water Reactors
Thomas K. S. Liang, Huan-Jen Hung, Chin-Jang Chang
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 292-300
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3246
Investigating the Stability Characteristics of Natural-Circulation Boiling Water Reactors Using Root Loci of a Reduced-Order Model
Robert Zboray, Wilhelmus J. M. de Kruijf, Tim H. J. J. van der Hagen, Hugo van Dam
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 301-314
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3247
Numerical Methodology to Evaluate Fast Reactor Sodium Combustion
Akira Yamaguchi, Takashi Takata, Yasushi Okano
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 315-330
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT01-A3248
Kinetic and Statistical Analysis of Primary Circuit Water Chemistry Data in a VVER Power Plant
Gabor Nagy, Péter Tilky, Ákos Horváth, Tamás Pintér, Robert Schiller
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 331-341
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT01-A3249
Separation of Actinides from LWR Spent Fuel Using Molten-Salt-Based Electrochemical Processes
Eric J. Karell, Karthick V. Gourishankar, James L. Smith, Lorac S. Chow, Laszlo Redey
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 342-353
Technical Paper | Reprocessing | doi.org/10.13182/NT136-342
Influence of Finite Absorption of Radionuclides on Radionuclide Migration in an Engineered Barrier System
Toshiaki Matsuo, Takuma Yoshida
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 354-366
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT01-A3251
The Influence of Lewis Acid/Base Chemistry on the Removal of Gallium by Volatility from Weapons-Grade Plutonium Dissolved in Molten Chlorides
David F. Williams, Guillermo D. Del Cul, Louis M. Toth, Emory D. Collins
Nuclear Technology | Volume 136 | Number 3 | December 2001 | Pages 367-370
Technical Note | Fuel Cycle and Management | doi.org/10.13182/NT01-A3252
