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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
2023 ANS Winter Conference and Expo
November 12–15, 2023
Washington, D.C.|Washington Hilton
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 2023
Jan 2023
Latest Journal Issues
Nuclear Science and Engineering
October 2023
Nuclear Technology
Fusion Science and Technology
Latest News
NRC moves ahead on HALEU enrichment, rulemaking, and guidance
The Nuclear Regulatory Commission is requesting comments on the regulatory basis for a proposed rule for light water reactor fuel designs featuring high-assay low-enriched uranium (HALEU), including accident tolerant fuel (ATF) designs, and on draft guidance for the environmental evaluation of ATFs containing uranium enriched up to 8 percent U-235. Some of the HALEU feedstock for those LWR fuels and for advanced reactor fuels could be produced within the first Category II fuel facility licensed by the NRC—Centrus Energy’s American Centrifuge Plant in Piketon, Ohio. On September 21, the NRC approved the start of enrichment operations in the plant’s modest 16-machine HALEU demonstration cascade.
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Rehomogenization of Nodal Cross Sections via Modal Synthesis of Neutron Spectrum Changes
Matteo Gamarino, Aldo Dall’Osso, Danny Lathouwers, Jan Leen Kloosterman
Nuclear Science and Engineering | Volume 190 | Number 1 | April 2018 | Pages 1-30
Technical Paper | doi.org/10.1080/00295639.2017.1417214
Eigenvalue Solvers for Modeling Nuclear Reactors on Leadership Class Machines
R. N. Slaybaugh, M. Ramirez-Zweiger, Tara Pandya, Steven Hamilton, T. M. Evans
Nuclear Science and Engineering | Volume 190 | Number 1 | April 2018 | Pages 31-44
Technical Paper | doi.org/10.1080/00295639.2017.1413875
A Linear Prolongation Approach to Stabilizing CMFD
Dean Wang, Sicong Xiao
Nuclear Science and Engineering | Volume 190 | Number 1 | April 2018 | Pages 45-55
Technical Paper | doi.org/10.1080/00295639.2017.1417347
Variance Reduction and Optimization Strategies in a Biased Woodcock Particle Tracking Framework
Balazs Molnar, Gabor Tolnai, David Legrady
Nuclear Science and Engineering | Volume 190 | Number 1 | April 2018 | Pages 56-72
Technical Paper | doi.org/10.1080/00295639.2017.1413876
Stability and Bifurcation Characteristics of a Forced Circulation BWR Using a Nuclear-Coupled Homogeneous Thermal-Hydraulic Model
Dinkar Verma, Subhanker Paul, Pankaj Wahi
Nuclear Science and Engineering | Volume 190 | Number 1 | April 2018 | Pages 73-92
Technical Paper | doi.org/10.1080/00295639.2017.1407593
Experimental and Numerical Investigations on Heat Transfer of Reactor Internals Under Direct Injection
Yu Weng, Fangfang Cao, Xiaobing Tuo, Hongfang Gu, Haijun Wang
Nuclear Science and Engineering | Volume 190 | Number 1 | April 2018 | Pages 93-104
Technical Paper | doi.org/10.1080/00295639.2017.1417345
Second-Order Sensitivity Analysis of Uncollided Particle Contributions to Radiation Detector Responses
Dan G. Cacuci, Jeffrey A. Favorite
Nuclear Science and Engineering | Volume 190 | Number 2 | May 2018 | Pages 105-133
Technical Paper | doi.org/10.1080/00295639.2018.1426899
Improved Variational Nodal Method Based on Symmetry Group Theory
Yunzhao Li, Zhipeng Li, Hongchun Wu, Youqi Zheng
Nuclear Science and Engineering | Volume 190 | Number 2 | May 2018 | Pages 134-155
Technical Paper | doi.org/10.1080/00295639.2017.1417346
The Improvement of Coupling Method in TINTE by Fully Implicit Scheme
Han Zhang, Jiong Guo, Jianan Lu, Fu Li, Yunlin Xu, T. J. Downar
Nuclear Science and Engineering | Volume 190 | Number 2 | May 2018 | Pages 156-175
Technical Paper | doi.org/10.1080/00295639.2018.1426299
Limiting Surface Density Method Adapted to Large Arrays of Heterogeneous Shipping Packages with Nonlinear Responses
Tracy E. Stover, James S. Baker, Michael D. Ratliff, Gretchen C. Mitschelen
Nuclear Science and Engineering | Volume 190 | Number 2 | May 2018 | Pages 176-194
Technical Paper | doi.org/10.1080/00295639.2017.1417344
Experimental Investigation on the Effect of Spacer on the Turbulent Mixing in Vertical Pressure Tube–Type Boiling Water Reactor
Shashi Kant Verma, S. L. Sinha, D. K. Chandraker
Nuclear Science and Engineering | Volume 190 | Number 2 | May 2018 | Pages 195-208
Technical Paper | doi.org/10.1080/00295639.2017.1413874
Development and Benchmarking of Mechanistic Channel Deformation Models in RELAP/SCDAPSIM/MOD3.6 for CANDU Severe Accident Analysis
F. Zhou, D. R. Novog, L. J. Siefken, C. M. Allison
Nuclear Science and Engineering | Volume 190 | Number 3 | June 2018 | Pages 209-237
Technical Paper | doi.org/10.1080/00295639.2018.1442060
Jacobian-Free Newton-Krylov Nodal Expansion Methods with Physics-Based Preconditioner and Local Elimination for Three-Dimensional and Multigroup k-Eigenvalue Problems
Xiafeng Zhou, Fu Li
Nuclear Science and Engineering | Volume 190 | Number 3 | June 2018 | Pages 238-257
Technical Paper | doi.org/10.1080/00295639.2018.1435136
Identifying Inconsistencies in Fission Product Yield Evaluations with Prompt Neutron Emission
Patrick Jaffke
Nuclear Science and Engineering | Volume 190 | Number 3 | June 2018 | Pages 258-270
Technical Paper | doi.org/10.1080/00295639.2018.1429173
Uncertainty Quantification Study of CTF for the OECD/NEA LWR Uncertainty Analysis in Modeling Benchmark
Nathan W. Porter, Maria N. Avramova, Vincent A. Mousseau
Nuclear Science and Engineering | Volume 190 | Number 3 | June 2018 | Pages 271-286
Technical Paper | doi.org/10.1080/00295639.2018.1435135
An Assessment of Coupling Algorithms in HTR Simulator TINTE
Nuclear Science and Engineering | Volume 190 | Number 3 | June 2018 | Pages 287-309
Technical Paper | doi.org/10.1080/00295639.2018.1442061
