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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
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 Technology
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February 2023
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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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Analysis of Reactivity Coefficients of Hydride-Fueled PWR Cores
Francesco Ganda, Ehud Greenspan
Nuclear Science and Engineering | Volume 164 | Number 1 | January 2010 | Pages 1-32
Technical Paper | doi.org/10.13182/NSE08-64
Fourier Convergence Analysis of the Rebalance Methods for Discrete Ordinates Transport Equations in Eigenvalue Problems
Ser Gi Hong, Kang-Seog Kim, Jae Seung Song
Nuclear Science and Engineering | Volume 164 | Number 1 | January 2010 | Pages 33-52
Technical Paper | doi.org/10.13182/NSE09-18
Power Distribution Analysis for the ORNL High Flux Isotope Reactor Critical Experiment 3
David Chandler, R. T. Primm III, G. Ivan Maldonado
Nuclear Science and Engineering | Volume 164 | Number 1 | January 2010 | Pages 53-68
Technical Paper | doi.org/10.13182/NSE09-03
Neutron Detection-Based Void Monitoring in Boiling Water Reactors
John Loberg, Michael Österlund, Jan Blomgren, Klaes-Håkan Bejmer
Nuclear Science and Engineering | Volume 164 | Number 1 | January 2010 | Pages 69-79
Technical Paper | doi.org/10.13182/NSE09-17
Calculation of the Integral Kinetic Model Transient Parameters by the Monte Carlo Method for Space-Dependent Kinetic Analysis
Hiroki Takezawa, Toru Obara
Nuclear Science and Engineering | Volume 164 | Number 1 | January 2010 | Pages 80-86
Technical Note | doi.org/10.13182/NSE08-91
Daubechies' Wavelet Method for Angular Solution of the Neutron Transport Equation
Youqi Zheng, Hongchun Wu, Liangzhi Cao, Nam Zin Cho
Nuclear Science and Engineering | Volume 164 | Number 2 | February 2010 | Pages 87-104
Technical Paper | doi.org/10.13182/NSE09-21
The Inner-Element Subgrid Scale Finite Element Method for the Boltzmann Transport Equation
Andrew G. Buchan, Adam S. Candy, Simon R. Merton, Christopher C. Pain, Justin I. Hadi, Matthew D. Eaton, Anthony J. H. Goddard, Richard P. Smedley-Stevenson, Gregory J. Pearce
Nuclear Science and Engineering | Volume 164 | Number 2 | February 2010 | Pages 105-121
Technical Paper | doi.org/10.13182/NSE08-82
Polynomial Regression Approaches Using Derivative Information for Uncertainty Quantification
Oleg Roderick, Mihai Anitescu, Paul Fischer
Nuclear Science and Engineering | Volume 164 | Number 2 | February 2010 | Pages 122-139
Technical Paper | doi.org/10.13182/NSE08-79
Computing the Matrix Exponential in Burnup Calculations
Maria Pusa, Jaakko Leppänen
Nuclear Science and Engineering | Volume 164 | Number 2 | February 2010 | Pages 140-150
Technical Paper | doi.org/10.13182/NSE09-14
Determination of Operator Action Times During a Loss-of-Feedwater Event Using Extreme Value Statistics
A. C. Morreale, D. R. Novog
Nuclear Science and Engineering | Volume 164 | Number 2 | February 2010 | Pages 151-161
Technical Paper | doi.org/10.13182/NSE08-16
Reactivity Effects of Differences Between JEFF-3.1 and ENDF/B-VI.8 in Analysis of Six MASURCA Cores of the R-Z Program
Michael A. Pope, Jean Tommasi
Nuclear Science and Engineering | Volume 164 | Number 2 | February 2010 | Pages 162-184
Technical Paper | doi.org/10.13182/NSE09-22
Double-Differential Cross Sections of the Particle Emission in Neutron-Induced Reactions on 209Bi
Yinlu Han, Ping Liu, Chonghai Cai
Nuclear Science and Engineering | Volume 164 | Number 2 | February 2010 | Pages 185-203
Technical Paper | doi.org/10.13182/NSE09-20
Discontinuous Least-Squares Spatial Discretization Schemes for the One-Dimensional Slab-Geometry Sn Equations
Lei Zhu, Jim E. Morel
Nuclear Science and Engineering | Volume 164 | Number 3 | March 2010 | Pages 205-220
Technical Paper | doi.org/10.13182/NSE08-67
A Three-Dimensional Block-Oriented Hybrid Discrete Ordinates and Characteristics Method
Ce Yi, Alireza Haghighat
Nuclear Science and Engineering | Volume 164 | Number 3 | March 2010 | Pages 221-247
Technical Paper | doi.org/10.13182/NSE09-110
Fourier Analysis of Inexact Parallel Block-Jacobi Splitting with Transport Synthetic Acceleration
Massimiliano Rosa, James S. Warsa, Jae H. Chang
Nuclear Science and Engineering | Volume 164 | Number 3 | March 2010 | Pages 248-263
Technical Paper | doi.org/10.13182/NSE09-26
Finite Element Analysis of Transient Heat Transfer in and Around a Deep Geological Repository for a Spent Nuclear Fuel Disposal Canister and the Heat Generation of the Spent Nuclear Fuel
Young Joo Kwon
Nuclear Science and Engineering | Volume 164 | Number 3 | March 2010 | Pages 264-286
Technical Paper | doi.org/10.13182/NSE09-11
Resonance Parameters and Uncertainties Derived from Epithermal Neutron Capture and Transmission Measurements of Natural Molybdenum
G. Leinweber, D. P. Barry, J. A. Burke, N. J. Drindak, Y. Danon, R. C. Block, N. C. Francis, B. E. Moretti
Nuclear Science and Engineering | Volume 164 | Number 3 | March 2010 | Pages 287-303
Technical Paper | doi.org/10.13182/NSE08-76
Recalculation and Reevaluation of the Complete Sets of Neutron Data for 63Cu and 65Cu Below 20 MeV
Chonghai Cai, Kai Xu, Haixia An, Haicheng Wu
Nuclear Science and Engineering | Volume 164 | Number 3 | March 2010 | Pages 304-317
Technical Note | doi.org/10.13182/NSE08-62TN
