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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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 Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
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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
