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Division Spotlight
Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
Meeting Spotlight
Nuclear and Emerging Technologies for Space (NETS 2023)
May 7–11, 2023
Idaho Falls, ID|Snake River Event Center
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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Nuclear power developments in China and the world
The development of human society and technology is closely correlated to the means of energy acquisition, utilization method, efficiency, and spectrum of applications. High quality of life and sustainable socioeconomic development require a sustainable and reliable energy supply. Wealth, health, food, water, infrastructure, education, and even life expectancy itself strongly correlate with the consumption of energy per capita. Having an adequate, reliable, affordable, eco-friendly, and sustainable supply of energy is becoming more crucial for economic development and improving human well-being.
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Exploration of an Analytical Model for Treating the Unresolved Resonances
R. N. Hwang
Nuclear Science and Engineering | Volume 167 | Number 1 | January 2011 | Pages 1-39
Technical Paper | doi.org/10.13182/NSE10-004
An Adaptive Energy Mesh Constructor for Multigroup Library Generation for Transport Codes
Pietro Mosca, Claude Mounier, Richard Sanchez, Gilles Arnaud
Nuclear Science and Engineering | Volume 167 | Number 1 | January 2011 | Pages 40-60
Technical Paper | doi.org/10.13182/NSE10-10
Reactor Kinetics, Dynamic Response, and Neutron Noise in Molten Salt Reactors
I. Pázsit, A. Jonsson
Nuclear Science and Engineering | Volume 167 | Number 1 | January 2011 | Pages 61-76
Technical Paper | doi.org/10.13182/NSE10-15
A Five-Year Core for a Small Modular Light Water Reactor
Alexey Soldatov, Todd S. Palmer
Nuclear Science and Engineering | Volume 167 | Number 1 | January 2011 | Pages 77-90
Technical Paper | doi.org/10.13182/NSE09-39
A Zero-Variance-Based Scheme for Monte Carlo Criticality Calculations
Stavros Christoforou, J. Eduard Hoogenboom
Nuclear Science and Engineering | Volume 167 | Number 1 | January 2011 | Pages 91-104
Technical Paper | doi.org/10.13182/NSE09-107
Analysis of Coolant Void Reactivity of Advanced Heavy Water Reactor Through Isotopic Reaction Rates
Kannan Umasankari, S. Ganesan
Nuclear Science and Engineering | Volume 167 | Number 2 | February 2011 | Pages 105-121
Technical Paper | doi.org/10.13182/NSE10-17
Application of the Jacobian-Free Newton-Krylov Method to Nonlinear Acceleration of Transport Source Iteration in Slab Geometry
D. A. Knoll, H. Park, Kord Smith
Nuclear Science and Engineering | Volume 167 | Number 2 | February 2011 | Pages 122-132
Technical Paper | doi.org/10.13182/NSE09-75
Acceleration of k-Eigenvalue/Criticality Calculations Using the Jacobian-Free Newton-Krylov Method
D. A. Knoll, H. Park, C. Newman
Nuclear Science and Engineering | Volume 167 | Number 2 | February 2011 | Pages 133-140
Technical Paper | doi.org/10.13182/NSE09-89
Newton's Method for Solving k-Eigenvalue Problems in Neutron Diffusion Theory
Daniel F. Gill, Yousry Y. Azmy
Nuclear Science and Engineering | Volume 167 | Number 2 | February 2011 | Pages 141-153
Technical Paper | doi.org/10.13182/NSE09-98
Comparison of Different Numerical Methods Used in Delayed Neutron Decay Parameters Estimation
Jinkai Wang, Warren D. Reece
Nuclear Science and Engineering | Volume 167 | Number 2 | February 2011 | Pages 154-164
Technical Paper | doi.org/10.13182/NSE09-94
Biases and Statistical Errors in Monte Carlo Burnup Calculations: An Unbiased Stochastic Scheme to Solve Boltzmann/Bateman Coupled Equations
E. Dumonteil, C. M. Diop
Nuclear Science and Engineering | Volume 167 | Number 2 | February 2011 | Pages 165-170
Technical Paper | doi.org/10.13182/NSE09-100
Calculation of the (, n) Emission from Plutonium Nitrate and Plutonium Uranyl Nitrate Solutions
M. T. Swinhoe
Nuclear Science and Engineering | Volume 167 | Number 2 | February 2011 | Pages 171-175
Technical Paper | doi.org/10.13182/NSE09-97
A Monte Carlo Lattice Code with Probability Tables and Optimized Energy Meshes
Nicolas Martin, Alain Hébert
Nuclear Science and Engineering | Volume 167 | Number 3 | March 2011 | Pages 177-195
Technical Paper | doi.org/10.13182/NSE10-45
Uncertainty Propagation in Monte Carlo Depletion Analysis
Ho Jin Park, Hyung Jin Shim, Chang Hyo Kim
Nuclear Science and Engineering | Volume 167 | Number 3 | March 2011 | Pages 196-208
Technical Paper | doi.org/10.13182/NSE09-106
Reactivity Perturbation Formulation for a Discontinuous Galerkin-Based Transport Solver and Its Use with Adaptive Mesh Refinement
R. Le Tellier, D. Fournier, C. Suteau
Nuclear Science and Engineering | Volume 167 | Number 3 | March 2011 | Pages 209-220
Technical Paper | doi.org/10.13182/NSE10-34
Simulations and Models of Neutron Fluxes in Boiling Water Reactors Intended for Depletion Calculations of Withdrawn Control Rods
John Loberg, Michael Österlund, Klaes-Håkan Bejmer, Jan Blomgren, Jesper Kierkegaard, Sten-Örjan Lindahl
Nuclear Science and Engineering | Volume 167 | Number 3 | March 2011 | Pages 221-229
Technical Paper | doi.org/10.13182/NSE09-105
Application of CASMO-4/MICROBURN-B2 Methodology to Mixed Cores with Westinghouse Optima2 Fuel
Ming-Yuan Hsiao, John K. Wheeler, Carlos de la Hoz
Nuclear Science and Engineering | Volume 167 | Number 3 | March 2011 | Pages 230-241
Technical Paper | doi.org/10.13182/NSE10-18
Effects of He++ Ion Irradiation on Adhesion of Polymer Microstructure-Based Dry Adhesives
Paul Day, Mark Cutkosky, Richard Greco, Anastasia McLaughlin
Nuclear Science and Engineering | Volume 167 | Number 3 | March 2011 | Pages 242-247
Technical Note | doi.org/10.13182/NSE10-56TN
