ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Sep 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
November 2024
Nuclear Technology
October 2024
Fusion Science and Technology
Latest News
NRC restores expiration dates for renewed Turkey Point licenses
The Nuclear Regulatory Commission announced this week that it has restored the expiration dates of the Turkey Point nuclear power plant's units 3 and 4 subsequent license renewals (SLR) to July 19, 2052, and April 10, 2053, respectively.
Jump to:
Experimental and Computational Forensics Characterization of Weapons-Grade Plutonium Produced in a Fast Reactor Neutron Environment
Mathew W. Swinney, Charles M. Folden III, Ronald J. Ellis, Sunil S. Chirayath
Nuclear Technology | Volume 197 | Number 1 | January 2017 | Pages 1-11
Technical Paper | doi.org/10.13182/NT16-76
Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotopes in Modeling of BR3 Reactor Spent Fuel
Andrew Conant, Anna Erickson, Martin Robel, Brett Isselhardt
Nuclear Technology | Volume 197 | Number 1 | January 2017 | Pages 12-19
Technical Paper | doi.org/10.13182/NT16-88
A Probabilistic Hazard Assessment Framework for Safety-Critical and Control Systems: A Case Study for a Nuclear Power Plant
Vinay Kumar, Lalit Singh, A. K. Tripathi
Nuclear Technology | Volume 197 | Number 1 | January 2017 | Pages 20-28
Technical Paper | doi.org/10.13182/NT16-89
Core Design Studies of a Fast Reactor and Accelerator-Driven System for Two-Stage Fast Spectrum Fuel Cycle Option
Ching-Sheng Lin, Tongkyu Park, Won Sik Yang
Nuclear Technology | Volume 197 | Number 1 | January 2017 | Pages 29-46
Technical Paper | doi.org/10.13182/NT16-90
Rod Internal Pressure Distribution and Uncertainty Analysis Using FRAPCON
Ryan N. Bratton, Matt A. Jessee, William A. Wieselquist, Kostadin N. Ivanov
Nuclear Technology | Volume 197 | Number 1 | January 2017 | Pages 47-63
Technical Paper | doi.org/10.13182/NT16-75
Passive Reactivity Control of Nuclear Thermal Propulsion Reactors
Paolo F. Venneri, Michael Eades, Yonghee Kim
Nuclear Technology | Volume 197 | Number 1 | January 2017 | Pages 64-74
Technical Paper | doi.org/10.13182/NT16-80
Study on a Low-Cost and Large-Scale Environmentally Adaptive Protocol Stack of Nuclear and Space Wireless Sensor Network Applications Under Gamma Radiation
Yu Liu, Michael Nishimura, Liqian Li, Karen Colins
Nuclear Technology | Volume 197 | Number 1 | January 2017 | Pages 75-87
Technical Paper | doi.org/10.13182/NT16-97
Removal of Antimony over Nano Titania–Impregnated Epichlorohydrin-Crosslinked Chitosan Beads from a Typical Decontamination Formulation
Padala Abdul Nishad, Anupkumar Bhaskarapillai, Sankaralingam Velmurugan
Nuclear Technology | Volume 197 | Number 1 | January 2017 | Pages 88-98
Technical Paper | doi.org/10.13182/NT16-77
Studies on Dissolution Behavior of the Surface Layer of Sodium-Exposed SS 316LN in Decontaminating Formulation Using PEMHS
C. Ramesh, N. Murugesan, V. Ganesan, N. Sivai Bharasi, M. G. Pujar, U. Kamachi Mudali
Nuclear Technology | Volume 197 | Number 1 | January 2017 | Pages 99-109
Technical Paper | doi.org/10.13182/NT15-141
Reactivity Measurement Using the Area-Ratio Method in the BRAHMMA Subcritical System
Nirmal Kumar Ray, Tushar Roy, Shefali Bajpai, Tarun Patel, Yogesh Kashyap, Mayank Shukla, Amar Sinha
Nuclear Technology | Volume 197 | Number 1 | January 2017 | Pages 110-115
Technical Note | doi.org/10.13182/NT16-71
Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward
Charles W. Forsberg, Stephen Lam, David M. Carpenter, Dennis G. Whyte, Raluca Scarlat, Cristian Contescu, Liu Wei, John Stempien, Edward Blandford
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 119-139
Critical Review | doi.org/10.13182/NT16-101
Prediction of Countercurrent Flow Limitation and Its Uncertainty in Horizontal and Slightly Inclined Pipes
Michio Murase, Yoichi Utanohara, Takayoshi Kusunoki, Yasunori Yamamoto, Dirk Lucas, Akio Tomiyama
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 140-157
Technical Paper | doi.org/10.13182/NT16-96
Experimental Investigation of Void Drift in Simulated Subchannels of a Natural-Circulation Pressure Tube–Type BWR
M. P. Sharma, A. K. Nayak
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 158-170
Technical Paper | doi.org/10.13182/NT15-127
Modeling of Water Ingression Mechanism for Corium Cooling with MELCOR
Tuomo Sevón
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 171-179
Technical Paper | doi.org/10.13182/NT16-108
Technical Basis for the Use of a Correlated Neutron Source in the Uranium Neutron Coincidence Collar
M. A. Root, H. O. Menlove, R. C. Lanza, C. D. Rael, K. A. Miller, J. B. Marlow
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 180-190
Technical Paper | doi.org/10.13182/NT16-50
Thermal Conductivity Measurement of Granular UO2(NO3)2 · 6H2O
Gary M. Stange, Michael Corradini, Robert Swader, George Petry, Thomas R. Mackie, Kevin W. Eliceiri
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 191-200
Technical Paper | doi.org/10.13182/NT16-107
Nuclear Radiation-Tolerant Wireless Transmitter Irradiation Test Results
Jorge V. Carvajal, Michael D. Heibel, Nicola G. Arlia, Andrew Bascom, Kenan Ünlü
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 201-208
Technical Paper | doi.org/10.13182/NT16-92
Some Mathematical and Geophysical Considerations in Radioisotope Dating Applications
Robert B. Hayes
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 209-218
Technical Paper | doi.org/10.13182/NT16-98
Removal of Cesium from Simulated Radioactive Wastewater Using a Novel Disc Tubular Reverse Osmosis System
Fei Jia, Jufeng Li, Jianlong Wang, Yuliang Sun
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 219-224
Technical Note | doi.org/10.13182/NT16-6
Multiunit Accident Contributions to Quantitative Health Objectives: A Safety Goal Policy Analysis
Daniel W. Hudson, Mohammad Modarres
Nuclear Technology | Volume 197 | Number 3 | March 2017 | Pages 227-247
Technical Paper | doi.org/10.1080/00295450.2016.1273714
Approaches to a Practical Systems Assessment for Safeguardability of Advanced Nuclear Fuel Cycles
R. A. Borrelli, Joonhang Ahn, Yongsoo Hwang
Nuclear Technology | Volume 197 | Number 3 | March 2017 | Pages 248-264
Technical Paper | doi.org/10.1080/00295450.2016.1273713
BWR Control Rod Drift Analysis Capability in the U.S. NRC Core Simulator PATHS/PARCS
P. Yarsky, Y. Xu, A. Ward, N. Hudson, T. Downar
Nuclear Technology | Volume 197 | Number 3 | March 2017 | Pages 265-283
Technical Paper | doi.org/10.1080/00295450.2016.1273707
Evaluation of the Pool Critical Assembly Benchmark with Explicitly Modeled Geometry Using MCNP6
Joel A. Kulesza, Roger L. Martz
Nuclear Technology | Volume 197 | Number 3 | March 2017 | Pages 284-295
Technical Paper | doi.org/10.1080/00295450.2016.1273711
Security Analysis of Safety Critical and Control Systems: A Case Study of a Nuclear Power Plant System
Raj Kamal Kaur, Lalit Kumar Singh, Babita Pandey
Nuclear Technology | Volume 197 | Number 3 | March 2017 | Pages 296-307
Technical Paper | doi.org/10.1080/00295450.2016.1273702
An Interactive Reverse-Engineering Cyclic Voltammetry for Uranium Electrochemical Studies in LiCl-KCl Eutectic Salt
Samaneh Rakhshan Pouri, Supathorn Phongikaroon
Nuclear Technology | Volume 197 | Number 3 | March 2017 | Pages 308-319
Technical Paper | doi.org/10.1080/00295450.2016.1273730
Effect of Radiation on the Transmission Rate of Emission Intensity of Optical Fiber Cable Used in a Nuclear Material Facility
Daewoong Choi, Bo-Young Han, Se Hwan Park, Ho-dong Kim, Geun-il Park, Jeong-Hoe Ku
Nuclear Technology | Volume 197 | Number 3 | March 2017 | Pages 320-328
Technical Note | doi.org/10.1080/00295450.2016.1273701
Real-Time In-Pile Acoustic Measurement Infrastructure at the Advanced Test Reactor
Vivek Agarwal, James A. Smith
Nuclear Technology | Volume 197 | Number 3 | March 2017 | Pages 329-333
NT Letter | doi.org/10.1080/00295450.2016.1273704