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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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June 2025
Nuclear Technology
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May 2025
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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
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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
