ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Terrestrial Energy looks at EnergySolutions-owned sites for IMSR plants
Advanced reactor developer Terrestrial Energy and Utah-based waste management company EnergySolutions announced they have signed a memorandum of understanding to collaborate on the siting and deployment of Terrestrial Energy’s integral molten salt reactor plants at EnergySolutions-owned sites.
Jump to:
On the Evaluation of Discrepant Scientific Data with Unrecognized Errors
Dan G. Cacuci, Mihaela Ionescu-Bujor
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 1-17
Technical Paper | doi.org/10.13182/NSE09-37A
Best-Estimate Model Calibration and Prediction Through Experimental Data Assimilation—I: Mathematical Framework
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 18-44
Technical Paper | doi.org/10.13182/NSE09-37B
Best-Estimate Model Calibration and Prediction Through Experimental Data Assimilation - II: Application to a Blowdown Benchmark Experiment
Alessandro Petruzzi, Dan G. Cacuci, Francesco D'Auria
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 45-100
Technical Paper | doi.org/10.13182/NSE09-37C
Scaled and Full-Size Three-Loop Reactor Vessel Simulation for Boron Dilution Studies Using Computational Fluid Dynamics
T. V. Dury, M. T. Dhotre
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 101-116
Technical Paper | doi.org/10.13182/NSE08-90
The 235U(n,f) Prompt Fission Neutron Spectrum at 100 K Input Neutron Energy
N. Kornilov, F.-J. Hambsch, I. Fabry, S. Oberstedt, T. Belgya, Z. Kis, L. Szentmiklosi, S. Simakov
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 117-127
Technical Paper | doi.org/10.13182/NSE09-25
Comments on “Numerical Stability of Existing Monte Carlo Burnup Codes in Cycle Calculations of Critical Reactors”
Gray S. Chang
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 128-130
Letter to the Editor | doi.org/10.13182/NSE09-58L
Reply to “Comments on ‘Numerical Stability of Existing Monte Carlo Burnup Codes in Cycle Calculations of Critical Reactors’”
Jan Dufek
Nuclear Science and Engineering | Volume 165 | Number 1 | May 2010 | Pages 130-131
Letter to the Editor | doi.org/10.13182/NSE09-58R
Nonlinear Weighted Flux Methods for Particle Transport Problems in Two-Dimensional Cartesian Geometry
Loren Roberts, Dmitriy Y. Anistratov
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 133-148
Technical Paper | doi.org/10.13182/NSE08-48
Asymptotic Diffusion-Limit Accuracy of Sn Angular Differencing Schemes
Teresa S. Bailey, Jim E. Morel, Jae H. Chang
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 149-169
Technical Paper | doi.org/10.13182/NSE08-66
Adaptive Three-Dimensional Monte Carlo Functional-Expansion Tallies
Brian C. Franke, Ronald P. Kensek
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 170-179
Technical Paper | doi.org/10.13182/NSE08-68
Transient Two-Dimensional Hydrodynamic Experiments
Aya Diab, Michael Corradini
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 180-199
Technical Paper | doi.org/10.13182/NSE08-18
Re-Analysis of Recent Neutron Diffusion and Transmission Measurements in Nuclear Graphite
C. R. Gould, A. I. Hawari, E. I. Sharapov
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 200-209
Technical Paper | doi.org/10.13182/NSE09-48
The Impact of Power Coastdown Operations on the Water Chemistry and Corrosion in Boiling Water Reactors
Tsung-Kuang Yeh, Mei-Ya Wang
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 210-223
Technical Paper | doi.org/10.13182/NSE09-27
Cross Sections for 239Pu(n,f) and 241Pu(n,f) in the Range En = 0.01 eV to 200 MeV
F. Tovesson, T. S. Hill
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 224-231
Technical Paper | doi.org/10.13182/NSE09-41
Recent Progress in the Design of a Tomographic Device for Measurements of the Three-Dimensional Pin-Power Distribution in Irradiated Nuclear Fuel Assemblies
Tobias Lundqvist Saleh, Staffan Jacobsson Svärd, Ane Håkansson, A. Bäcklin
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 232-239
Technical Note | doi.org/10.13182/NSE09-23TN
A Study of Photon Interaction and Photon Energy Absorption Effective Atomic Numbers for Some Amino Acids
Tejbir Singh, Updesh Kaur, Shivali Tandon, Parjit S. Singh
Nuclear Science and Engineering | Volume 165 | Number 2 | June 2010 | Pages 240-244
Technical Note | doi.org/10.13182/NSE09-35TN
Automated Design and Optimization of Pebble-Bed Reactor Cores
H. D. Gougar, A. M. Ougouag, W. K. Terry, K. N. Ivanov
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 245-269
Technical Paper | doi.org/10.13182/NSE08-89
Spatial Corrections for Pulsed-Neutron Reactivity Measurements
Yan Cao, John C. Lee
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 270-282
Technical Paper | doi.org/10.13182/NSE09-32
Exact Regional Monte Carlo Weight Cancellation for Second Eigenfunction Calculations
Thomas E. Booth, James E. Gubernatis
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 283-291
Technical Paper | doi.org/10.13182/NSE09-62
A Transport Acceleration Scheme for Multigroup Discrete Ordinates with Upscattering
Thomas M. Evans, Kevin T. Clarno, Jim E. Morel
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 292-304
Technical Paper | doi.org/10.13182/NSE09-28
Goal-Oriented h-Adaptivity for the Multigroup SPN Equations
Bruno Turcksin, Jean C. Ragusa, Wolfgang Bangerth
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 305-319
Technical Paper | doi.org/10.13182/NSE09-34
Extension of Differential Operator Method to Inhomogeneous Problems with Internal and External Neutron Sources
Kirill Fedorovich Raskach
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 320-330
Technical Paper | doi.org/10.13182/NSE09-47
The Newton-Krylov Method Applied to Negative-Flux Fixup in SN Transport Calculations
Erin D. Fichtl, James S. Warsa, Jeffery D. Densmore
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 331-341
Technical Paper | doi.org/10.13182/NSE09-51
