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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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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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Two-Dimensional Geometrical Corner Singularities in Neutron Diffusion--Part I: Analysis
Dan G. Cacuci
Nuclear Science and Engineering | Volume 128 | Number 1 | January 1998 | Pages 1-16
Technical Paper | doi.org/10.13182/NSE98-A1941
Two-Dimensional Geometrical Corner Singularities in Neutron Diffusion--Part II: Application to the SNR-300 Benchmark
D. G. Cacuci, E. Kiefhaber, B. Stehle
Nuclear Science and Engineering | Volume 128 | Number 1 | January 1998 | Pages 17-26
Technical Paper | doi.org/10.13182/NSE98-A1942
The Time-Dependent Simplified P2 Equations: Asymptotic Analyses and Numerical Experiments
Uncheol Shin, Warren F. Miller, Jr.
Nuclear Science and Engineering | Volume 128 | Number 1 | January 1998 | Pages 27-46
Technical Paper | doi.org/10.13182/NSE98-A1943
Measured and Calculated Differential and Total Yield Cross-Section Data of 58Ni(n,x) and 63Cu(n,xp) in the Neutron Energy Range from 2.0 to 15.6 MeV
C. Tsabaris, E. Wattecamps, G. Rollin, C. Papadopoulos
Nuclear Science and Engineering | Volume 128 | Number 1 | January 1998 | Pages 47-60
Technical Paper | doi.org/10.13182/NSE128-47
Neutron Total Cross-Section Measurements and Resonance Parameter Analysis of Holmium, Thulium, and Erbium from 0.001 to 20 eV
Y. Danon, C. J. Werner, G. Youk, R. C. Block, R. E. Slovacek, N. C. Francis, J. A. Burke, N. J. Drindak, F. Feiner, J. A. Helm
Nuclear Science and Engineering | Volume 128 | Number 1 | January 1998 | Pages 61-69
Technical Paper | doi.org/10.13182/NSE98-A1945
Transmutation of Technetium in the Petten High Flux Reactor: A Comparison of Measurements and Calculations
R. J. M. Konings, J. L. Kloosterman, J. A. Hendriks, H. Gruppelaar
Nuclear Science and Engineering | Volume 128 | Number 1 | January 1998 | Pages 70-75
Technical Paper | doi.org/10.13182/NSE98-A1946
Calculation of Point-Kinetics Parameters in the MOBY-DICK System
Jirí Svarný, Václav Krýysl, Pavel Mikolás, Karel Vlachovský
Nuclear Science and Engineering | Volume 128 | Number 1 | January 1998 | Pages 76-87
Technical Paper | doi.org/10.13182/NSE98-A1947
The Scalar Flux and Current for Small Critical One-Dimensional Systems
G. C. Pomraning
Nuclear Science and Engineering | Volume 128 | Number 1 | January 1998 | Pages 88-91
Technical Note | doi.org/10.13182/NSE98-A1948
The Mol-7C In-Pile Local Blockage Experiments: Main Results, Conclusions, and Extrapolation to Reactor Conditions
K. Schleisiek, J. Aberle, Ch. Homann, I. Schmuck, W. Maschek, A. Rahn, O. Romer, L. Schmidt, L. Borms, A. Verwimp
Nuclear Science and Engineering | Volume 128 | Number 2 | February 1998 | Pages 93-143
Technical Paper | doi.org/10.13182/NSE98-A1949
Summary of the SCARABEE-N Subassembly Melting and Propagation Tests with an Application to a Hypothetical Total Instantaneous Blockage in a Reactor
Gaston Kayser, Jean Charpenel, Claude Jamond
Nuclear Science and Engineering | Volume 128 | Number 2 | February 1998 | Pages 144-185
Technical Paper | doi.org/10.13182/NSE98-A1950
Automated Variance Reduction of Monte Carlo Shielding Calculations Using the Discrete Ordinates Adjoint Function
John C. Wagner, Alireza Haghighat
Nuclear Science and Engineering | Volume 128 | Number 2 | February 1998 | Pages 186-208
Technical Paper | doi.org/10.13182/NSE98-2
On the Equivalence of Boundary and Boundary Condition Perturbations in Transport Theory and Its Diffusion Approximation
Farzad Rahnema, Piero Ravetto
Nuclear Science and Engineering | Volume 128 | Number 2 | February 1998 | Pages 209-223
Technical Paper | doi.org/10.13182/NSE98-A1952
Noise Decomposition in Boiling Water Reactors with Application to Stability Monitoring
J. Karlsson, I. Pázsit
Nuclear Science and Engineering | Volume 128 | Number 3 | March 1998 | Pages 225-242
Technical Paper | doi.org/10.13182/NSE98-A1953
Analyses of the Thermal Hydraulics in the NUPEC 1/4-Scale Model Containment Experiments
Douglas W. Stamps
Nuclear Science and Engineering | Volume 128 | Number 3 | March 1998 | Pages 243-269
Technical Paper | doi.org/10.13182/NSE98-A1954
Measurements of Absolute Delayed Neutron Yield and Group Constants in the Fast Fission of 235U and 237Np
David J. Loaiza, Glenn Brunson, Rene Sanchez, Ken Butterfield
Nuclear Science and Engineering | Volume 128 | Number 3 | March 1998 | Pages 270-277
Technical Paper | doi.org/10.13182/NSE98-A1955
A Nonlinear Corner-Balance Spatial Discretization for Transport on Arbitrary Grids
Chris L. Castrianni, Marvin L. Adams
Nuclear Science and Engineering | Volume 128 | Number 3 | March 1998 | Pages 278-296
Technical Paper | doi.org/10.13182/NSE98-A1956
Development of a Numerical Experiment Technique to Solve Inverse Gamma-Ray Transport Problems with Application to Nondestructive Assay of Nuclear Waste Barrels
Chin-Jen Chang, Samim Anghaie
Nuclear Science and Engineering | Volume 128 | Number 3 | March 1998 | Pages 297-311
Technical Paper | doi.org/10.13182/NSE98-A1957
An Sn Algorithm for the Massively Parallel CM-200 Computer
Randal S. Baker, Kenneth R. Koch
Nuclear Science and Engineering | Volume 128 | Number 3 | March 1998 | Pages 312-320
Technical Note | doi.org/10.13182/NSE98-1
Neutron Cross-Section Probability Tables in TRIPOLI-3 Monte Carlo Transport Code
S. H. Zheng, T. Vergnaud, J. C. Nimal
Nuclear Science and Engineering | Volume 128 | Number 3 | March 1998 | Pages 321-328
Technical Note | doi.org/10.13182/NSE98-A1959
