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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
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A Priori Deterministic Computational-Cost Optimization of Weight-Dependent Variance-Reduction Parameters for Monte Carlo Neutral-Particle Transport
C. J. Solomon, A. Sood, T. E. Booth, J. K. Shultis
Nuclear Science and Engineering | Volume 176 | Number 1 | January 2014 | Pages 1-36
Technical Paper | doi.org/10.13182/NSE12-81
FW-CADIS Method for Global and Regional Variance Reduction of Monte Carlo Radiation Transport Calculations
John C. Wagner, Douglas E. Peplow, Scott W. Mosher
Nuclear Science and Engineering | Volume 176 | Number 1 | January 2014 | Pages 37-57
Technical Paper | doi.org/10.13182/NSE12-33
Real Variance Estimation by Grouping Histories in Monte Carlo Eigenvalue Calculations
Hyung Jin Shim, Sung Hoon Choi, Chang Hyo Kim
Nuclear Science and Engineering | Volume 176 | Number 1 | January 2014 | Pages 58-68
Technical Paper | doi.org/10.13182/NSE12-87
High-Order Perturbation Theory for Incident Flux Response Expansion Methods
Dingkang Zhang, Farzad Rahnema
Nuclear Science and Engineering | Volume 176 | Number 1 | January 2014 | Pages 69-80
Technical Paper | doi.org/10.13182/NSE13-1
Calibration and Improved Prediction of Computer Models by Universal Kriging
François Bachoc, Guillaume Bois, Josselin Garnier, Jean-Marc Martinez
Nuclear Science and Engineering | Volume 176 | Number 1 | January 2014 | Pages 81-97
Technical Paper | doi.org/10.13182/NSE12-55
Measured F(α,n) Yield from 234U in Uranium Hexafluoride
Karen A. Miller, Martyn T. Swinhoe, Stephen Croft, Takayuki Tamura, Shun Aiuchi, Akio Kawai, Tomonori Iwamoto
Nuclear Science and Engineering | Volume 176 | Number 1 | January 2014 | Pages 98-105
Technical Paper | doi.org/10.13182/NSE12-43
Fission Product Yield in the Neutron-Induced Fission of 232Th with Average Energies of 5.42, 7.75, and 10.09 MeV
P. M. Prajapati, H. Naik, S. Mukherjee, S. V. Suryanarayana, B. S. Shivashankar, R. Crasta, V. K. Mulik, K. C. Jagadeesan, S. V. Thakre, S. Ganesan, A. Goswami
Nuclear Science and Engineering | Volume 176 | Number 1 | January 2014 | Pages 106-113
Technical Paper | doi.org/10.13182/NSE12-78
A Review on Sodium Boiling Phenomena in Reactor Systems
Matthias Vanderhaegen, Alix Le Belguet
Nuclear Science and Engineering | Volume 176 | Number 2 | February 2014 | Pages 115-137
Technical Paper | doi.org/10.13182/NSE12-99
Numerical Study of Compact Heat Exchanger Designs for Generation IV Supercritical Carbon Dioxide Power Conversion Cycles
Bryce K. Y. Matsuo, Mark Anderson, Devesh Ranjan
Nuclear Science and Engineering | Volume 176 | Number 2 | February 2014 | Pages 138-153
Technical Paper | doi.org/10.13182/NSE12-85
Numerical Solutions of the Poisson Equation: Condensation/Evaporation on Arbitrarily Shaped Aerosols
Z. M. Smith, S. K. Loyalka
Nuclear Science and Engineering | Volume 176 | Number 2 | February 2014 | Pages 154-166
Technical Paper | doi.org/10.13182/NSE12-107
Computational Evaluation of Neutron Multiplicity Measurements of Polyethylene-Reflected Plutonium Metal
E. C. Miller, J. K. Mattingly, S. D. Clarke, C. J. Solomon, B. Dennis, A. Meldrum, S. A. Pozzi
Nuclear Science and Engineering | Volume 176 | Number 2 | February 2014 | Pages 167-185
Technical Paper | doi.org/10.13182/NSE12-53
The Development and Implementation of a One-Dimensional Sn Method in the 2D-1D Integral Transport Solution
M. Hursin, B. Collins, Y. Xu, T. Downar
Nuclear Science and Engineering | Volume 176 | Number 2 | February 2014 | Pages 186-200
Technical Paper | doi.org/10.13182/NSE12-4
Diffusion Acceleration Schemes for Self-Adjoint Angular Flux Formulation with a Void Treatment
Yaqi Wang, Hongbin Zhang, Richard C. Martineau
Nuclear Science and Engineering | Volume 176 | Number 2 | February 2014 | Pages 201-225
Technical Paper | doi.org/10.13182/NSE12-83
Multicycle Fuel Loading Pattern Optimization by Multiobjective Simulated Annealing Employing Adaptively Constrained Discontinuous Penalty Function
Tong Kyu Park, Han Gyu Joo, Chang Hyo Kim
Nuclear Science and Engineering | Volume 176 | Number 2 | February 2014 | Pages 226-239
Technical Paper | doi.org/10.13182/NSE12-41
A New Grid-Based Tomographic Method for Two-Phase Flow Measurements
Mayank Goswami, Anupam Saxena, Prabhat Munshi
Nuclear Science and Engineering | Volume 176 | Number 2 | February 2014 | Pages 240-253
Technical Paper | doi.org/10.13182/NSE12-26
Analyses of Material Effects on Steam Explosions in TROI FCI Tests
Ik Kyu Park, Jong Hwan Kim, Seong Wan Hong
Nuclear Science and Engineering | Volume 176 | Number 3 | March 2014 | Pages 255-272
Technical Paper | doi.org/10.13182/NSE13-16
A Coarse-Mesh Method for the Time-Dependent Transport Equation
Justin M. Pounders, Farzad Rahnema
Nuclear Science and Engineering | Volume 176 | Number 3 | March 2014 | Pages 273-291
Technical Paper | doi.org/10.13182/NSE12-108
Consistent Spatial Homogenization in Transport Theory
Saam Yasseri, Farzad Rahnema
Nuclear Science and Engineering | Volume 176 | Number 3 | March 2014 | Pages 292-311
Technical Paper | doi.org/10.13182/NSE13-9
A Presentation of the OPTEX Reflector Model
Alain Hébert, Hadrien Leroyer
Nuclear Science and Engineering | Volume 176 | Number 3 | March 2014 | Pages 312-324
Technical Paper | doi.org/10.13182/NSE13-26
Sensitivity Analysis and Data Assimilation in a Subcritical Plutonium Metal Benchmark
Richard T. Evans, John K. Mattingly, Dan G. Cacuci
Nuclear Science and Engineering | Volume 176 | Number 3 | March 2014 | Pages 325-338
Technical Paper | doi.org/10.13182/NSE13-24
Reducing Uncertainties via Predictive Modeling: FLICA4 Calibration Using BFBT Benchmarks
Dan G. Cacuci, Erkan Arslan
Nuclear Science and Engineering | Volume 176 | Number 3 | March 2014 | Pages 339-349
Technical Paper | doi.org/10.13182/NSE13-31
Analytic Model for Dead Time Effect in Neutron Multiplicity Counting
C. Dubi, I. Israelashvili, T. Ridnik
Nuclear Science and Engineering | Volume 176 | Number 3 | March 2014 | Pages 350-359
Technical Paper | doi.org/10.13182/NSE13-2
Molecular Dynamics Simulation of Thermodynamic Properties in Uranium Dioxide
Xiangyu Wang, Bin Wu, Fei Gao, Xin Li, Xin Sun, Mohammed A. Khaleel, Ademola V. Akinlalu, Li Liu
Nuclear Science and Engineering | Volume 176 | Number 3 | March 2014 | Pages 360-369
Technical Paper | doi.org/10.13182/NSE13-14
G4-STORK: A Monte Carlo Reactor Kinetics Simulation Code
Liam Russell, Adriaan Buijs, Guy Jonkmans
Nuclear Science and Engineering | Volume 176 | Number 3 | March 2014 | Pages 370-375
Computer Code Abstract | doi.org/10.13182/NSE13-8