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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
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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Optimizing Maintenance Strategies in Power Generation: Embracing Predictive and Preventive Approaches
In the high-stakes world of power generation, ensuring continuous operation and reducing downtime are central priorities. With the increasing complexity of power generation systems, maintenance practices are evolving to meet these demands more efficiently. Understanding the roles of Predictive Maintenance (PdM), Preventive Maintenance (PM), and Reactive Maintenance (Run-to-Failure) is crucial for maintenance professionals in the energy sector to make informed decisions about equipment management and long-term operational strategy.
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Time Interval Distributions and the Rossi Correlation Function
M. Prasad, N. Snyderman, J. Verbeke, R. Wurtz
Nuclear Science and Engineering | Volume 174 | Number 1 | May 2013 | Pages 1-29
Technical Paper | doi.org/10.13182/NSE11-87
Kernel Density Estimation Method for Monte Carlo Point Detector and Surface Crossing Flux Tallies
Kaushik Banerjee, William R. Martin
Nuclear Science and Engineering | Volume 174 | Number 1 | May 2013 | Pages 30-45
Technical Paper | doi.org/10.13182/NSE11-94
Analysis of KROTOS Steam Explosion Experiments Using the Improved Fuel-Coolant-Interaction Code TEXAS-VI
R. H. Chen, M. L. Corradini, G. H. Su, S. Z. Qiu
Nuclear Science and Engineering | Volume 174 | Number 1 | May 2013 | Pages 46-59
Technical Paper | doi.org/10.13182/NSE12-22
Simulation of Unsteady Flow Through a String of CANDU Fuel Bundles in a Pressure Tube
A. Bhattacharya, S. D. Yu
Nuclear Science and Engineering | Volume 174 | Number 1 | May 2013 | Pages 60-78
Technical Paper | doi.org/10.13182/NSE12-31
Quadratic Depletion Method for Gadolinium Isotopes in CASMO-5
Deokjung Lee, Joel Rhodes, Kord Smith
Nuclear Science and Engineering | Volume 174 | Number 1 | May 2013 | Pages 79-86
Technical Paper | doi.org/10.13182/NSE12-20
A Novel, Robust Control Methodology Application to Nuclear Reactors
Hassan M. Emara, Adel A. Hanafy, Magdy M. Zaky Abdelaal, Sayed Elaraby
Nuclear Science and Engineering | Volume 174 | Number 1 | May 2013 | Pages 87-95
Technical Paper | doi.org/10.13182/NSE12-8
Instrumentation for Sodium-Cooled Fast Breeder Reactors
Govind Kumar Mishra, M. Sakthivel, S. L. N. Swamy, K. Madhusoodanan
Nuclear Science and Engineering | Volume 174 | Number 1 | May 2013 | Pages 96-102
Technical Note | doi.org/10.13182/NSE10-74
Monte Carlo Investigation on the Average Prompt Neutron Multiplicity as a Function of the Total Kinetic Energy and Mass of the Fragments from 252Cf Spontaneous Fission
David Regnier, Olivier Litaize, Olivier Serot
Nuclear Science and Engineering | Volume 174 | Number 1 | May 2013 | Pages 103-108
Technical Note | doi.org/10.13182/NSE12-12
Multicell Correction Method for Treatment of Heterogeneities in Full-Core Calculation of CANDU-Type Reactors
Wei Shen, Dimitar Altiparmakov
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 109-134
Technical Paper | doi.org/10.13182/NSE12-42
Neutronic Analysis of the Oregon State TRIGA Reactor in Support of Conversion from HEU Fuel to LEU Fuel
M. R. Hartman, S. T. Keller, S. R. Reese, B. Robinson, J. Stevens, J. E. Matos, W. R. Marcum, T. S. Palmer, B. G. Woods
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 135-149
Technical Paper | doi.org/10.13182/NSE12-5
Multilevel NDA Methods for Solving Multigroup Eigenvalue Neutron Transport Problems
Dmitriy Y. Anistratov
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 150-162
Technical Paper | doi.org/10.13182/NSE12-28
Unstructured Triangular Nodal-SP3 Method Based on an Exponential Function Expansion
Yunzhao Li, Hongchun Wu, Liangzhi Cao
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 163-171
Technical Paper | doi.org/10.13182/NSE11-111
Stochastic Eigenvalues in Multiplying Systems
M. M. R. Williams
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 172-178
Technical Paper | doi.org/10.13182/NSE12-45
Predicted Water Chemistry in the Primary Coolant Circuit of a Supercritical Water Reactor
Mei-Ya Wang, Tsung-Kuang Yeh, Hong-Ming Liu, Min Lee
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 179-187
Technical Paper | doi.org/10.13182/NSE12-16
Quasi-Differential Neutron Scattering in Zirconium from 0.5 to 20 MeV
D. P. Barry, G. Leinweber, R. C. Block, T. J. Donovan, Y. Danon, F. J. Saglime, A. M. Daskalakis, M. J. Rapp, R. M. Bahran
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 188-201
Technical Paper | doi.org/10.13182/NSE12-1
Measurements of Isomeric Cross Sections for (n,) Reaction on 144Sm Isotope for Neutrons Around 14 MeV
Iskender Atilla Reyhancan, Ayse Durusoy
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 202-207
Technical Paper | doi.org/10.13182/NSE11-96
A Cellwise Block-Gauss-Seidel Iterative Method for Multigroup SN Transport on a Hybrid Parallel Computer Architecture
Massimiliano Rosa, James S. Warsa, Michael Perks
Nuclear Science and Engineering | Volume 174 | Number 3 | July 2013 | Pages 209-226
Technical Paper | doi.org/10.13182/NSE12-57
Adjoint-Based k-Eigenvalue Sensitivity Coefficients to Nuclear Data Using Continuous-Energy Monte Carlo
Brian C. Kiedrowski, Forrest B. Brown
Nuclear Science and Engineering | Volume 174 | Number 3 | July 2013 | Pages 227-244
Technical Paper | doi.org/10.13182/NSE12-46
Diffusion Theory-Based Analog Monte Carlo for Simulating Noise Experiments in Subcritical Systems
Y. S. Rana, Arun Singh, S. B. Degweker
Nuclear Science and Engineering | Volume 174 | Number 3 | July 2013 | Pages 245-263
Technical Paper | doi.org/10.13182/NSE11-117
Prediction of Pebble Motion in Pebble-Bed Reactors Using Monte Carlo Molecular Dynamics Simulation
Kyoung O. Lee, Robin P. Gardner
Nuclear Science and Engineering | Volume 174 | Number 3 | July 2013 | Pages 264-285
Technical Paper | doi.org/10.13182/NSE12-23
Hybrid Monte Carlo-CMFD Methods for Accelerating Fission Source Convergence
Emily R. Wolters, Edward W. Larsen, William R. Martin
Nuclear Science and Engineering | Volume 174 | Number 3 | July 2013 | Pages 286-299
Technical Paper | doi.org/10.13182/NSE12-72
Impact of Dynamic Condensation of Energy Groups on Convergence Behavior of One-Node CMFD Method for Neutron Diffusion Problem
Deokjung Lee
Nuclear Science and Engineering | Volume 174 | Number 3 | July 2013 | Pages 300-317
Technical Paper | doi.org/10.13182/NSE12-27
Modeling of Nonuniform Density Distributions in the Serpent 2 Monte Carlo Code
Jaakko Leppänen
Nuclear Science and Engineering | Volume 174 | Number 3 | July 2013 | Pages 318-325
Technical Paper | doi.org/10.13182/NSE12-54
