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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
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Model Development for Risk-Based Safety Assessment of a Geological Disposal System of Radioactive Wastes Generated by Pyroprocessing of Pressurized Water Reactor Spent Fuel in Korea
Jung-Woo Kim, Dong-Keun Cho, Nak-Youl Ko, Jongtae Jeong, Min-Hoon Baik
Nuclear Technology | Volume 203 | Number 1 | July 2018 | Pages 1-16
Technical Paper | doi.org/10.1080/00295450.2018.1426331
Numerical Modeling and Experimental Validation of Melt Pool Coolability Under Bottom Flooding with Decay Heat Simulation
Nitendra Singh, Arun K. Nayak, Parimal P. Kulkarni
Nuclear Technology | Volume 203 | Number 1 | July 2018 | Pages 17-33
Technical Paper | doi.org/10.1080/00295450.2018.1426961
Using the Time-Correlated Induced Fission Method to Simultaneously Measure the 235U Content and the Burnable Poison Content in LWR Fuel Assemblies
M. A. Root, H. O. Menlove, R. C. Lanza, C. D. Rael, K. A. Miller, J. B. Marlow, J. G. Wendelberger
Nuclear Technology | Volume 203 | Number 1 | July 2018 | Pages 34-47
Technical Paper | doi.org/10.1080/00295450.2018.1429112
Development of the Tritium Transport Analysis Code for the Thorium-Based Molten Salt Reactor
Youshi Zeng, Shengwei Wu, Wei Liu, Guanghua Wang, Nan Qian, Xiaoling Wu, Wenguan Liu, Yu Huang, Yuan Qian
Nuclear Technology | Volume 203 | Number 1 | July 2018 | Pages 48-57
Technical Paper | doi.org/10.1080/00295450.2018.1433408
Verification of Modelica-Based Models with Analytical Solutions for Tritium Diffusion
Jordan D. Rader, M. Scott Greenwood, Paul W. Humrickhouse
Nuclear Technology | Volume 203 | Number 1 | July 2018 | Pages 58-65
Technical Paper | doi.org/10.1080/00295450.2018.1431505
A Scoping Study of the Chemical Behavior of Cesium Iodide in the Presence of Boron in the Condensed Phase (650°C and 400°C) Under Primary Circuit Conditions
Mélany Gouëllo, Jouni Hokkinen, Teemu Kärkelä, Ari Auvinen
Nuclear Technology | Volume 203 | Number 1 | July 2018 | Pages 66-84
Technical Paper | doi.org/10.1080/00295450.2018.1429111
A Complementary Study of the Chemical Behavior of Cesium Iodide in the Presence of Boron in the Condensed Phase (650°C and 400°C) Under Primary Circuit Conditions: Differential Thermal Analysis and Thermogravimetric Studies
Nuclear Technology | Volume 203 | Number 1 | July 2018 | Pages 85-91
Technical Paper | doi.org/10.1080/00295450.2018.1430463
Assessment of Parameters of Radioactive Aerosol Release Through Air Duct System Using the SOCRAT/V3 Code
R. V. Arutyunyan, D. A. Pripachkin, K. S. Dolganov, S. V. Tsaun, S. N. Krasnoperov, D. V. Aron, D. Yu. Tomashchik, E. L. Serebryakov, S. V. Panchenko, A. V. Shikin
Nuclear Technology | Volume 203 | Number 1 | July 2018 | Pages 92-100
Technical Paper | doi.org/10.1080/00295450.2018.1432839
Treatment of Radioactive Wastewater from High-Temperature Gas-Cooled Reactor by Membrane System
Junfeng Li, Shuting Zhuang, Liang Wang, Jianlong Wang
Nuclear Technology | Volume 203 | Number 1 | July 2018 | Pages 101-107
Technical Note | doi.org/10.1080/00295450.2018.1432838
Experimentally Known Properties of U-10Zr Alloys: A Critical Review
Dawn E. Janney, Steven L. Hayes
Nuclear Technology | Volume 203 | Number 2 | August 2018 | Pages 109-128
Critical Review | doi.org/10.1080/00295450.2018.1435137
Safety Analysis of a 300-MW(electric) Offshore Floating Nuclear Power Plant in Marine Environment
Yaoli Zhang, Jacopo Buongiorno, Michael Golay, Neil Todreas
Nuclear Technology | Volume 203 | Number 2 | August 2018 | Pages 129-145
Technical Paper | doi.org/10.1080/00295450.2018.1433935
Simulations of Pressure-Tube–Heavy-Water Reactor Cores Fueled with Thorium-Based Mixed-Oxide Fuels
Ashlea V. Colton, Blair P. Bromley
Nuclear Technology | Volume 203 | Number 2 | August 2018 | Pages 146-172
Technical Paper | doi.org/10.1080/00295450.2018.1444898
Steady-State Subchannel Thermal-Hydraulic Assessment of Proposed Thorium Fuel Designs
A. Nava Dominguez, Y. F. Rao
Nuclear Technology | Volume 203 | Number 2 | August 2018 | Pages 173-193
Technical Paper | doi.org/10.1080/00295450.2018.1442085
Numerical Study of Integral Inherently Safe Light Water Reactor in Case of Inadvertent DHR Operation Based on the Multiscale Method
Mingjun Wang, Annalisa Manera, Victor Petrov, Suizheng Qiu, Wenxi Tian, G. H. Su
Nuclear Technology | Volume 203 | Number 2 | August 2018 | Pages 194-204
Technical Paper | doi.org/10.1080/00295450.2018.1446656
Preliminary Waste Characterization Measurements in FiR 1 TRIGA Research Reactor Decommissioning Project
Antti Räty, Tommi Kekki, Merja Tanhua-Tyrkkö, Tiina Lavonen, Emmi Myllykylä
Nuclear Technology | Volume 203 | Number 2 | August 2018 | Pages 205-220
Technical Paper | doi.org/10.1080/00295450.2018.1445402
Seismic Probabilistic Risk Analysis and Application in a Nuclear Power Plant
Jinkai Wang, Modi Lin
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 221-231
Technical Paper | doi.org/10.1080/00295450.2018.1448671
Resource Demand and Economic Impact of Various Thorium-Based Fuels for Potential Near-Term Use in a Pressure-Tube Heavy Water Reactor
Alberto D. Mendoza España, Daniel Wojtaszek, Ashlea V. Colton, Blair P. Bromley
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 232-243
Technical Paper | doi.org/10.1080/00295450.2018.1447209
Development of a Validation Approach for an Integrated Waste Glass Melter Model
Donna Post Guillen, Alexander W. Abboud, Richard Pokorny, William C. Eaton, Derek Dixon, Kevin Fox, Albert A. Kruger
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 244-260
Technical Paper | doi.org/10.1080/00295450.2018.1458559
Parameter Surveys on Glass-Bonded Sodalite Synthesis Conditions from Spent Salt Generated in Pyroprocess
Koichi Uozumi, Kenji Fujihata, Takeshi Tsukada
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 261-271
Technical Paper | doi.org/10.1080/00295450.2018.1454807
Phase Equilibria Studies of the LiCl-KCl-UCl3 System
Amber L. Hames, Alena Paulenova, James L. Willit, Mark A. Williamson
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 272-281
Technical Paper | doi.org/10.1080/00295450.2018.1448673
Mechanical Property Degradation of Unirradiated Zircaloy-4 Cladding After Creep Deformation
Jong-Dae Hong, Euijung Kim, Yong-Sik Yang, Dong-Hak Kook
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 282-292
Technical Paper | doi.org/10.1080/00295450.2018.1448203
Unsteady Single-Phase Natural-Circulation Flow Mixing Prediction Using 3-D Thermal-Hydraulic System and CFD Codes
A. Bousbia Salah, S. C. Ceuca, R. Puragliesi, R. Mukin, A. Grahn, S. Kliem, J. Vlassenbroeck, H. Austregesilo
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 293-314
Technical Paper | doi.org/10.1080/00295450.2018.1461517
Vibration Effect Induced by Acoustic Pressure for UDV Measurement in Small Flow Channel
Shaoqiu Huang, Zhiqiang Zhu, Wangli Huang, Jian He, Jie Yu
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 315-324
Technical Paper | doi.org/10.1080/00295450.2018.1460126
A Methodology for Determining the Concentration of Naturally Occurring Radioactive Materials in an Urban Environment
Mathew W. Swinney, Douglas E. Peplow, Bruce W. Patton, Andrew D. Nicholson, Daniel E. Archer, Michael J. Willis
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 325-335
Technical Paper | doi.org/10.1080/00295450.2018.1458558
Adhesion Force Measurements: Graphite Cluster Interacting with VHTR Steel
Naphtali M. Mokgalapa, Tushar K. Ghosh, Robert V. Tompson, Sudarshan K. Loyalka
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 336-347
Technical Note | doi.org/10.1080/00295450.2018.1453729
