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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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Error Estimations and Their Biases in Monte Carlo Eigenvalue Calculations
Taro Ueki, Takamasa Mori and Masayuki Nakagawa
Nuclear Science and Engineering | Volume 125 | Number 1 | January 1997 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE97-1
Post-Convergence Automatic Differentiation of Iterative Schemes
Yousry Y. Azmy
Nuclear Science and Engineering | Volume 125 | Number 1 | January 1997 | Pages 12-18
Technical Paper | doi.org/10.13182/NSE97-A24250
Perturbation of General Boundary Condition for an Eigenvalue Change in the Neutron Boltzmann Transport Equation
Toshihiro Yamamoto
Nuclear Science and Engineering | Volume 125 | Number 1 | January 1997 | Pages 19-23
Technical Paper | doi.org/10.13182/NSE97-A24251
The Suite of Analytical Benchmarks for Neutral Particle Transport in Infinite Isotropically Scattering Media
Drew E. Kornreich, B. D. Ganapol
Nuclear Science and Engineering | Volume 125 | Number 1 | January 1997 | Pages 24-50
Technical Paper | doi.org/10.13182/NSE97-A24252
Measurements of Delayed Neutron Decay Constants and Fission Yields from 235U, 237Np, 241Am, and 243Am
Habeeb H. Saleh, Theodore A. Parish, S. Raman, Nobuo Shinohara
Nuclear Science and Engineering | Volume 125 | Number 1 | January 1997 | Pages 51-60
Technical Paper | doi.org/10.13182/NSE97-A24253
Study of Total Discrete Gamma Radiation from Aluminum Under 14.9-MeV Neutron Bombardment
Hongyu Zhou, Guangshun Huang
Nuclear Science and Engineering | Volume 125 | Number 1 | January 1997 | Pages 61-74
Technical Paper | doi.org/10.13182/NSE97-A24254
The Role of Heater Thermal Response in Reactor Thermal Limits During Oscillatory Two-Phase Flows
A. E. Ruggles, A. D. Vasil’ev, N. W. Brown, M. W. Wendel
Nuclear Science and Engineering | Volume 125 | Number 1 | January 1997 | Pages 75-83
Technical Paper | doi.org/10.13182/NSE97-A24255
An Estimation of the Energy Generation Potential of Proton-Driven Subcritical ThO2 Lattices
Meir Segev, A. Galperin
Nuclear Science and Engineering | Volume 125 | Number 1 | January 1997 | Pages 84-92
Technical Paper | doi.org/10.13182/NSE97-A24256
Sensitivity Study of the Positive Scram Effect Relevant to the Chernobyl Accident Simulation
A. D’Angelo
Nuclear Science and Engineering | Volume 125 | Number 1 | January 1997 | Pages 93-100
Technical Paper | doi.org/10.13182/NSE97-A24257
A New Variational Functional for Space-Time Neutronics
J. A. Favorite, W. M. Stacey, Jr.
Nuclear Science and Engineering | Volume 125 | Number 1 | January 1997 | Pages 101-106
Technical Note | doi.org/10.13182/NSE97-A24258
Response Functions for Neutron Skyshine Analysis
Ah Auu Gui, J. Kenneth Shultis, Richard E. Faw
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 111-127
Technical Paper | doi.org/10.13182/NSE97-A24261
A New Weight-Dependent Direct Statistical Approach Model
K. W. Burn
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 128-170
Technical Paper | doi.org/10.13182/NSE97-A24262
The Generalized PN Synthetic Acceleration Method for Linear Transport Problems with Highly Anisotropic Scattering
Kassem M. Khattab
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 171-177
Technical Paper | doi.org/10.13182/NSE97-A24263
Resonance Calculations Using the Multiband Method and Interface Currents
Masahiro Tatsumi, Tomoko Ito, Toshikazu Takeda, Masatoshi Yamasaki, Akio Yamamoto, Masaharu Takayasu
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 178-187
Technical Paper | doi.org/10.13182/NSE97-A24264
A Geometry-Independent Fine-Mesh-Based Monte Carlo Importance Generator
Lianyan Liu, Robin P. Gardner
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 188-195
Technical Paper | doi.org/10.13182/NSE97-A24265
Study of Gamma Radiation from the Interaction of 14.6-MeV Neutrons with 27Al
S. Hlavá, L. Dostál, I. Turzo, A. Pavlik, H. Vonach
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 196-204
Technical Paper | doi.org/10.13182/NSE97-A24266
Measurement of Neutron Energy Spectrum Below 10 keV in an Iron Shield Bombarded by Deuterium-Tritium Neutrons and Benchmark Test of Evaluated Nuclear Data from 14 MeV to 1 eV
F. Maekawa, Y. Oyama
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 205-217
Technical Paper | doi.org/10.13182/NSE97-A24267
Positron-Emitting Radionuclide Yield in Deuterium Beam-Injected 3He Plasma
M. Yamagiwa
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 218-222
Technical Paper | doi.org/10.13182/NSE97-A24268
Experimental Study on Buoyancy-Driven Exchange Flows Through Breaches of a Tokamak Vacuum Vessel in a Fusion Reactor Under the Loss-of-Vacuum-Event Condition
Kazuyuki Takase, Kunugi Tomoaki, Masurou Ogawa, Yasushi Seki
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 223-231
Technical Paper | doi.org/10.13182/NSE97-A24269
Prediction of the Local Pressure Gradient During Partially Developed Subcooled Boiling in Research Reactors of High Power Density
Joel L. McDuffee, Arthur E. Ruggles
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 232-242
Technical Paper | doi.org/10.13182/NSE97-A24270
Validation of Neutron Fluence Calculation Methodology for VVER-440 Vessel
K. Ilieva, T. Apostolov, S. Belousov, Iv. Penev, I. Popova
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 243-247
Technical Paper | doi.org/10.13182/NSE97-A24271
Comparison of LAHET Code System Calculations with Experimental Results for Protons of Energies Less than 50 MeV Incident on Copper and Iron
S.L. Eaton, C.A. Beard, M. L. Adams
Nuclear Science and Engineering | Volume 125 | Number 3 | March 1997 | Pages 249-256
Technical Paper | doi.org/10.13182/NSE97-A24273
A Transport Synthetic Acceleration Method for Transport Iterations
Gilles L. Ramone, Marvin L. Adams, Paul F. Nowak
Nuclear Science and Engineering | Volume 125 | Number 3 | March 1997 | Pages 257-283
Technical Paper | doi.org/10.13182/NSE97-A24274
Error Analysis of the Nodal Expansion Method for Solving the Neutron Diffusion Equation
R. Christian Penland, Yousry Y. Azmy, Paul J. Turinsky
Nuclear Science and Engineering | Volume 125 | Number 3 | March 1997 | Pages 284-299
Technical Paper | doi.org/10.13182/NSE97-A24275
Parallel Processing of Two-Dimensional Sn Transport Calculations
Mikio Uematsu
Nuclear Science and Engineering | Volume 125 | Number 3 | March 1997 | Pages 300-313
Technical Paper | doi.org/10.13182/NSE97-A24276
Generalized Rayleigh Quotients for Eigenvalue Estimates of Neutron Balance Equations
H.N. M. Gheorghiu, F. Rahnema
Nuclear Science and Engineering | Volume 125 | Number 3 | March 1997 | Pages 314-323
Technical Paper | doi.org/10.13182/NSE97-A24277
Hierarchical Control of Reactor Inlet Temperature in Pool-Type Plants —I: Physics of Control
Richard B. Vilim, Humberto E. Garcia
Nuclear Science and Engineering | Volume 125 | Number 3 | March 1997 | Pages 324-336
Technical Paper | doi.org/10.13182/NSE97-A24278
Hierarchical Control of Reactor Inlet Temperature in Pool-Type Plants —II: Implementation and Results
Humberto E. Garcia, Richard B. Vilim, Eric M. Dean
Nuclear Science and Engineering | Volume 125 | Number 3 | March 1997 | Pages 337-347
Technical Paper | doi.org/10.13182/NSE97-A24279
Numerical Simulation of Flow Behaviors in the Loop Seal Using First-Principle Equations
Yuh-Ming Ferng
Nuclear Science and Engineering | Volume 125 | Number 3 | March 1997 | Pages 348-361
Technical Paper | doi.org/10.13182/NSE97-A24280
Thermal Breeding of Tritium: A Comparative Study of the Li + C and 3He + C Systems
Sanjay Gupta, Feroz Ahmed, Suresh Garg
Nuclear Science and Engineering | Volume 125 | Number 3 | March 1997 | Pages 362-370
Technical Paper | doi.org/10.13182/NSE97-A24281
Systematics of Isomeric Cross-Section Ratios for (n,2n), (n , p), (n, α) Reactions at 14.5 MeV
Xiaolong Huang, Dunjiu Cai
Nuclear Science and Engineering | Volume 125 | Number 3 | March 1997 | Pages 371-375
Technical Paper | doi.org/10.13182/NSE97-A24282
