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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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Some Improvements in State/Parameter Estimation Using the Cell-to-Cell Mapping Technique
Peng Wang, Tunc Aldemir
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 1-25
Technical Paper | doi.org/10.13182/NSE04-A2415
Krylov Subspace Iterations for Deterministic k-Eigenvalue Calculations
James S. Warsa, Todd A. Wareing, Jim E. Morel, John M. McGhee, Richard B. Lehoucq
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 26-42
Technical Paper | doi.org/10.13182/NSE04-1
Improvement of MERCURE-6's General Formalism for Calculating Gamma-Ray Buildup Factors in Multilayer Shields
Christophe Suteau, Maurice Chiron, Gilles Arnaud
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 43-55
Technical Paper | doi.org/10.13182/NSE04-A2417
A Model for Dead-Time Effects in Coincidence Counting
Ming-Shih Lu, Theodor Teichmann
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 56-62
Technical Paper | doi.org/10.13182/NSE04-A2418
A Systematics to Investigate the (n,) Cross Section with Energy Below 20 MeV Based on the Evaporation and Exciton Models
Sheng Fan, Xiaochun Shi, Fang Yan, Hongzhou Zhang, Zhixiang Zhao
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 63-72
Technical Paper | doi.org/10.13182/NSE04-A2419
Production of Neutrons with Protons of 22, 30, and 40 MeV in Stopping Targets of Carbon, Aluminum, Copper, Silver, Tantalum, and Lead
Thomas M. Amos, Robert R. Doering, Aaron Galonsky, Raj Jolly, Mary K. Zigrang
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 73-82
Technical Paper | doi.org/10.13182/NSE04-A2420
The Neutron Production Cross Sections for Pb, Bi, and Au Targets and Neutron Multiplicity for Nuclear Spallation Reaction Induced by 20- to 1600-MeV Protons
I. Demirkol, E. Tel, A. Arasoglu, A. Özmen, B. Sarer, A. Acir, M. Alkan
Nuclear Science and Engineering | Volume 147 | Number 1 | May 2004 | Pages 83-91
Technical Note | doi.org/10.13182/NSE04-A2421
Super-Nodal Methods for Space-Time Kinetics
Ugur Mertyurek, Paul J. Turinsky
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 93-126
Technical Paper | doi.org/10.13182/NSE04-A2422
Convergence Analysis of the Nonlinear Coarse-Mesh Finite Difference Method for One-Dimensional Fixed-Source Neutron Diffusion Problem
Deokjung Lee, Thomas J. Downar, Yonghee Kim
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 127-147
Technical Paper | doi.org/10.13182/NSE03-64
Optimized Algorithm for Collision Probability Calculations in Cubic Geometry
R. D. M. Garcia
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 148-157
Technical Paper | doi.org/10.13182/NSE04-A2424
Singular Solutions, Integral Transport Theory, and the Sn Method
J. E. Morel, K. D. Lathrop
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 158-166
Technical Paper | doi.org/10.13182/NSE04-A2425
Neutron Flux Distribution in a Cavity with a Point Source
Biplab Ghosh, S. B. Degweker
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 167-175
Technical Paper | doi.org/10.13182/NSE04-A2426
Acceleration of Response Matrix Method Using Cross-Section Scaling
Akio Yamamoto
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 176-184
Technical Paper | doi.org/10.13182/NSE04-A2427
Evaluation of the Efficiency of Gamma Spectrometers for Measuring Volumetric Samples
Nader M. A. Mohamed, M. Abou Mandour
Nuclear Science and Engineering | Volume 147 | Number 2 | June 2004 | Pages 185-188
Technical Paper | doi.org/10.13182/NSE04-A2428
A Comparative Review of Sensitivity and Uncertainty Analysis of Large-Scale Systems—I: Deterministic Methods
Mihaela Ionescu-Bujor, Dan G. Cacuci
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 189-203
Technical Paper | doi.org/10.13182/NSE03-105CR
A Comparative Review of Sensitivity and Uncertainty Analysis of Large-Scale Systems—II: Statistical Methods
Dan G. Cacuci, Mihaela Ionescu-Bujor
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 204-217
Technical Paper | doi.org/10.13182/04-54CR
Krylov Iterative Methods and the Degraded Effectiveness of Diffusion Synthetic Acceleration for Multidimensional SN Calculations in Problems with Material Discontinuities
James S. Warsa, Todd A. Wareing, Jim E. Morel
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 218-248
Technical Paper | doi.org/10.13182/NSE02-14
Discrete Ordinates Solutions for Highly Forward Peaked Scattering
Richard Sanchez, Norman J. McCormick
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 249-274
Technical Paper | doi.org/10.13182/NSE04-A2432
Unified Nodal Method for Solution to the Space-Time Kinetics Problems
Hyun Chul Lee, Ku Young Chung, Chang Hyo Kim
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 275-291
Technical Paper | doi.org/10.13182/NSE04-A2433
A Stochastic Problem Arising in the Storage of Radioactive Waste
M. M. R. Williams
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 292-306
Technical Paper | doi.org/10.13182/NSE04-A2434
Critical Experiments with Highly Enriched Uranium and Matrix Elements (Si, Mg, Al, Gd, and Fe)
Rene Sanchez, David Loaiza, Glenn Brunson, Robert Kimpland
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 307-318
Technical Paper | doi.org/10.13182/NSE04-A2435
Compression and Heating of a Gaseous Deuterium-Tritium Mixture by Means of Cascaded Light Gas Guns and Its Possible Application to Nuclear Fusion
D. Hofmann
Nuclear Science and Engineering | Volume 147 | Number 3 | July 2004 | Pages 319-322
Technical Note | doi.org/10.13182/NSE04-A2436
