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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
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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Mar 2023
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Nuclear Science and Engineering
May 2023
Nuclear Technology
April 2023
Fusion Science and Technology
February 2023
Latest News
Fortum, Outokumpu to investigate clean steel production with nuclear
Fortum—operator of Finland’s two-unit Loviisa nuclear power plant—has signed a memorandum of understanding with Finnish stainless steel producer Outokumpu to explore decarbonizing the latter’s manufacturing operations with the help of emerging nuclear technologies, the companies announced on March 23.
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On-the-Fly Generation of Differential Resonance Scattering Probability Distribution Functions for Monte Carlo Codes
Eva E. Davidson, William R. Martin
Nuclear Science and Engineering | Volume 187 | Number 1 | July 2017 | Pages 1-26
Technical Paper | doi.org/10.1080/00295639.2017.1294931
Transmutation Approximations for the Application of Hybrid Monte Carlo/Deterministic Neutron Transport to Shutdown Dose Rate Analysis
Elliott D. Biondo, Paul P. H. Wilson
Nuclear Science and Engineering | Volume 187 | Number 1 | July 2017 | Pages 27-48
Technical Paper | doi.org/10.1080/00295639.2016.1275848
A Depletion System Compression Method Based on Quantitative Significance Analysis
Yunzhao Li, Kai Huang, Hongchun Wu, Liangzhi Cao
Nuclear Science and Engineering | Volume 187 | Number 1 | July 2017 | Pages 49-69
Technical Paper | doi.org/10.1080/00295639.2017.1297079
Thick and Thin Target 7Li(p,n)7Be Neutron Spectra Below the Three-Body Breakup Reaction Threshold
Rebecca Pachuau, B. Lalremruata, N. Otuka, L. R. Hlondo, L. R. M. Punte, H. H. Thanga
Nuclear Science and Engineering | Volume 187 | Number 1 | July 2017 | Pages 70-80
Technical Paper | doi.org/10.1080/00295639.2017.1291053
High-Fidelity Modeling and Simulation for a High Flux Isotope Reactor Low-Enriched Uranium Core Design
Benjamin R. Betzler, David Chandler, Eva E. Davidson (née Sunny), Germina Ilas
Nuclear Science and Engineering | Volume 187 | Number 1 | July 2017 | Pages 81-99
Technical Paper | doi.org/10.1080/00295639.2017.1292090
Modeling and Validation of Temperature and Void Effects on Reactivity Experiments at the Missouri S&T Research Reactor
B. Richardson, J. King, A. Alajo, S. Usman, C. H. C. Giraldo
Nuclear Science and Engineering | Volume 187 | Number 1 | July 2017 | Pages 100-106
Technical Paper | doi.org/10.1080/00295639.2017.1292089
Calculations and Analysis of n+93Nb Reaction
Haiying Liang, Zhendong Wu, Zhengjun Zhang, Yinlu Han, Xuesheng Jiao
Nuclear Science and Engineering | Volume 187 | Number 2 | August 2017 | Pages 107-126
Technical Paper | doi.org/10.1080/00295639.2017.1295699
Impact of 235U Resonance Parameter Evaluation in the Reactivity Prediction
Luiz Leal, Adimir Dos Santos, Evgeny Ivanov, Tatiana Ivanova
Nuclear Science and Engineering | Volume 187 | Number 2 | August 2017 | Pages 127-141
Technical Paper | doi.org/10.1080/00295639.2017.1301739
Batch and History Sampling for Fixed-Source Monte Carlo Problems
Daniel B. Fromowitz
Nuclear Science and Engineering | Volume 187 | Number 2 | August 2017 | Pages 142-153
Technical Paper | doi.org/10.1080/00295639.2017.1312944
Monte Carlo Sensitivity and Uncertainty Analysis with Continuous-Energy Covariance Data
Dong Hyuk Lee, Hyung Jin Shim, Chang Hyo Kim
Nuclear Science and Engineering | Volume 187 | Number 2 | August 2017 | Pages 154-165
Technical Paper | doi.org/10.1080/00295639.2017.1307031
Neutronic Evaluation of a Liquid Salt–Cooled Reactor Assembly
Cole Gentry, G. Ivan Maldonado, Ondrej Chvala, Bojan Petrovic
Nuclear Science and Engineering | Volume 187 | Number 2 | August 2017 | Pages 166-184
Technical Paper | doi.org/10.1080/00295639.2017.1312931
Numerical Investigation on the Natural Circulation Thermal Hydraulic Characteristics of a Pressure Tube Type Boiling Water Reactor
Sapna Singh, Garima Singal, A. K. Nayak
Nuclear Science and Engineering | Volume 187 | Number 2 | August 2017 | Pages 185-201
Technical Paper | doi.org/10.1080/00295639.2017.1307048
Reactor Neutronics: Impact of Fissile Material
F. Heidet, R. N. Hill
Nuclear Science and Engineering | Volume 187 | Number 2 | August 2017 | Pages 202-211
Technical Paper | doi.org/10.1080/00295639.2017.1312933
Core Design and Analysis of Axially Heterogeneous Boiling Water Reactor for Burning Transuranium Elements
T. Hino, J. Miwa, T. Mitsuyasu, Y. Ishii, M. Ohtsuka, K. Moriya, K. Shirvan, V. Seker, A. Hall, T. Downar, P. M. Gorman, M. Fratoni, E. Greenspan
Nuclear Science and Engineering | Volume 187 | Number 3 | September 2017 | Pages 213-239
Technical Paper | doi.org/10.1080/00295639.2017.1312941
Coarse Mesh Rebalance Acceleration Applied to an Iterative Domain Decomposition Method on Unstructured Mesh
N. Odry, J.-J. Lautard, J.-F. Vidal, G. Rimpault
Nuclear Science and Engineering | Volume 187 | Number 3 | September 2017 | Pages 240-253
Technical Paper | doi.org/10.1080/00295639.2017.1320891
Verification of the Parallel Pin-Wise Core Simulator pCTF/PARCSv3.2 in Operational Control Rod Drop Transient Scenarios
Enrique Ramos, Jose E. Roman, Agustín Abarca, Rafael Miró, Juan A. Bermejo, Alberto Ortego, Jose M. Posada
Nuclear Science and Engineering | Volume 187 | Number 3 | September 2017 | Pages 254-267
Technical Paper | doi.org/10.1080/00295639.2017.1320892
MC2-3: Multigroup Cross Section Generation Code for Fast Reactor Analysis
Changho Lee, Won Sik Yang
Nuclear Science and Engineering | Volume 187 | Number 3 | September 2017 | Pages 268-290
Technical Paper | doi.org/10.1080/00295639.2017.1320893
Simultaneous Measurement of 235U Fission and Capture Cross Sections From 0.01 eV to 3 keV Using a Gamma Multiplicity Detector
Y. Danon, D. Williams, R. Bahran, E. Blain, B. McDermott, D. Barry, G. Leinweber, R. Block, M. Rapp
Nuclear Science and Engineering | Volume 187 | Number 3 | September 2017 | Pages 291-301
Technical Paper | doi.org/10.1080/00295639.2017.1312937
Measurement and Estimation of Cross Sections for 55Mn(n, γ)56Mn and 65Cu(n, γ)66Cu Reactions Using Accelerator-Based Neutron Source
Mehdi S. Barough, V. D. Bharud, B. J. Patil, F. M. D. Attar, V. N. Bhoraskar, S. D. Dhole
Nuclear Science and Engineering | Volume 187 | Number 3 | September 2017 | Pages 302-311
Technical Paper | doi.org/10.1080/00295639.2017.1323505
