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Division Spotlight
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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
Senate committee hears from energy secretary nominee Chris Wright
Wright
Chris Wright, president-elect Trump’s pick to lead the U.S. Department of Energy, spent hours today fielding questions from members of the U.S. Senate’s committee on Energy and Natural Resources.
During the hearing, Wright—who’s spent most of his career in fossil fuels—made comments in support of nuclear energy and efforts to expand domestic generation in the near future. Asked what actions he would take as energy secretary to improve the development and deployment of SMRs, Wright said: “It’s a big challenge, and I’m new to government, so I can’t list off the five levers I can pull. But (I’ve been in discussions) about how to make it easier to research, to invest, to build things. The DOE has land at some of its facilities that can be helpful in this regard.”
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Interaction of Neutrons with 9Be at 14.6 MeV — The Four-Body Breakup 2n + 2α
D. Ferenc, B. Antolković, G. Paić, M. Zadro, S. Blagus
Nuclear Science and Engineering | Volume 101 | Number 1 | January 1989 | Pages 1-7
Technical Paper | doi.org/10.13182/NSE89-A23590
Determination of the Field of View of a Boiling Water Reactor In-Core Detector
Alireza Haghighat, George Kosály
Nuclear Science and Engineering | Volume 101 | Number 1 | January 1989 | Pages 8-25
Technical Paper | doi.org/10.13182/NSE89-A23591
Vapor Pressure Measurements on Liquid Uranium Oxide and (U,Pu) Mixed Oxide
W. Breitung, K. O. Reil
Nuclear Science and Engineering | Volume 101 | Number 1 | January 1989 | Pages 26-40
Technical Paper | doi.org/10.13182/NSE89-A23592
On the Reactivity Effects of Nuclear Fuel Fragmentation with Reference to the Chernobyl Accident
Markku Rajamäki, Frej Wasastjerna
Nuclear Science and Engineering | Volume 101 | Number 1 | January 1989 | Pages 41-47
Technical Paper | doi.org/10.13182/NSE89-A23593
One-Dimensional Transient Fluid Model for Fuel/Coolant Interaction Analysis
C.C. Chu, M. L. Corradini
Nuclear Science and Engineering | Volume 101 | Number 1 | January 1989 | Pages 48-71
Technical Paper | doi.org/10.13182/NSE89-A23594
A Hybrid Collocation-Galerkin-Sn Method for Solving the Boltzmann Transport Equation
J. E. Morel
Nuclear Science and Engineering | Volume 101 | Number 1 | January 1989 | Pages 72-87
Technical Paper | doi.org/10.13182/NSE89-4
Evaluation of Correlated Data Using Partitioned Least Squares: A Minimum-Variance Derivation
D. W. Muir
Nuclear Science and Engineering | Volume 101 | Number 1 | January 1989 | Pages 88-93
Technical Note | doi.org/10.13182/NSE89-A23596
A New Evaluation of the Urania Equation of State Based on Recent Vapor Pressure Measurements
E. A. Fischer
Nuclear Science and Engineering | Volume 101 | Number 2 | February 1989 | Pages 97-116
Technical Paper | doi.org/10.13182/NSE89-A23600
Analytic Predictions of Boiling Film Stability for Conditions Consistent with Light Water Reactor Degraded Core Conditions
Man-Shik Song, Paul J. Turinsky
Nuclear Science and Engineering | Volume 101 | Number 2 | February 1989 | Pages 117-132
Technical Paper | doi.org/10.13182/NSE89-A23601
An Error Estimation for the Implicit Euler Method Recommended for Use in the RELAP4 Family of Codes
Stefan Goos
Nuclear Science and Engineering | Volume 101 | Number 2 | February 1989 | Pages 133-136
Technical Paper | doi.org/10.13182/NSE89-A23602
Benchmark Physics Tests in the Metallic-Fueled Assembly ZPPR-15
H. F. McFarlane, S. B. Brumbach, S. G. Carpenter, P. J. Collins
Nuclear Science and Engineering | Volume 101 | Number 2 | February 1989 | Pages 137-152
Technical Paper | doi.org/10.13182/NSE101-137
A Semianalytical Method to Solve the Linear Fokker-Planck Equation Characterizing Charged-Particle Transport in Spherical Plasmas
S. D. Paranjape, D. C. Sahni
Nuclear Science and Engineering | Volume 101 | Number 2 | February 1989 | Pages 153-165
Technical Paper | doi.org/10.13182/NSE89-A23604
Fine-Mesh Limit of One-Dimensional Nodal Transport Equations
Ely M. Gelbard, Yen-Wan H. Liu, Laura Olvey
Nuclear Science and Engineering | Volume 101 | Number 2 | February 1989 | Pages 166-178
Technical Paper | doi.org/10.13182/NSE89-A23605
Evaluation of Neutron Streaming in Fast Breeder Reactor Fuel Subassembly by Double Heterogeneous Modeling
Toshikazu Takeda, Hironobu Unesaki, Toshihisa Yamamoto, Katsuya Kinjo, Toshio Sanda
Nuclear Science and Engineering | Volume 101 | Number 2 | February 1989 | Pages 179-184
Technical Paper | doi.org/10.13182/NSE89-A23606
Transport Analysis of Measured Neutron Energy Spectra in a Graphite Stack with a Collimated Deuterium-Tritium Neutron Beam
R. Ofek, A. Tsechanski, A. Goldfeld, G. Shani
Nuclear Science and Engineering | Volume 101 | Number 2 | February 1989 | Pages 185-203
Technical Paper | doi.org/10.13182/NSE89-A23607
Vectorized and Multitasked Solution of the Few-Group Neutron Diffusion Equations
Sung-Kyun Zee, Paul J. Turinsky, Zeev Shayer
Nuclear Science and Engineering | Volume 101 | Number 3 | March 1989 | Pages 205-216
Technical Paper | doi.org/10.13182/NSE89-A23609
A Transport Method for Treating Three-Dimensional Lattices of Heterogeneous Cells
R. Roy, A. Hébert, G. Marleau
Nuclear Science and Engineering | Volume 101 | Number 3 | March 1989 | Pages 217-225
Technical Paper | doi.org/10.13182/NSE101-217
Analysis of Spectral Shift Effect on Reactor Dynamics and Its Application to RBMK-1000 and Light Water Reactors
Yoshiro Asahi, Tadashi Watanabe
Nuclear Science and Engineering | Volume 101 | Number 3 | March 1989 | Pages 226-242
Technical Paper | doi.org/10.13182/NSE89-A23611
A Study of the Multiplicity of Power Distributions in a Nuclear Reactor Subject to Reactivity Feedbacks
Chae Y. Yang, Nam Z. Cho
Nuclear Science and Engineering | Volume 101 | Number 3 | March 1989 | Pages 243-258
Technical Paper | doi.org/10.13182/NSE89-A23612
Modeling of an Aerosol in Coupled Chambers
D. R. Simpson, M. M. R. Williams, S. Simons
Nuclear Science and Engineering | Volume 101 | Number 3 | March 1989 | Pages 259-268
Technical Paper | doi.org/10.13182/NSE89-A23613
Role of Spatial Inhomogeneities in Source Term Aerosol Dynamics
J. W. Park, S. K. Loyalka
Nuclear Science and Engineering | Volume 101 | Number 3 | March 1989 | Pages 269-279
Technical Paper | doi.org/10.13182/NSE101-269
Fission-Fragment Energy Deposition in Argon
J. R. Torczynski, R. J. Gross, G. N. Hays, G. A. Harms, D. R. Neal, D. A. McArthur, W. J. Alford
Nuclear Science and Engineering | Volume 101 | Number 3 | March 1989 | Pages 280-284
Technical Paper | doi.org/10.13182/NSE89-A23615
Uncertainties of the ENDF/B-V 238U Unresolved Resonance Parameters in the Range 4 keV < E < 45.18 keV (MAT=1398, MF=2, MT=251)
G. de Saussure, J. H. Marable
Nuclear Science and Engineering | Volume 101 | Number 3 | March 1989 | Pages 285-292
Technical Paper | doi.org/10.13182/NSE89-A23616
Measurement of the Thermal Neutron Induced Fission Cross Section of 243Am
C. Wagemans, P. Schillebeeckx, J. P. Bocquet
Nuclear Science and Engineering | Volume 101 | Number 3 | March 1989 | Pages 293-297
Technical Paper | doi.org/10.13182/NSE89-A23617
New JEF/EFF Based MATXS-Formatted Nuclear Data Libraries
P. Vontobel, S. Pelloni
Nuclear Science and Engineering | Volume 101 | Number 3 | March 1989 | Pages 298-301
Technical Note | doi.org/10.13182/NSE89-A23618
Numerical Integration of Hydraulic Network Conservation Equations on MIMD Parallel Computers
Prem N. Mahana, F. N. Trofimenkoff
Nuclear Science and Engineering | Volume 101 | Number 4 | April 1989 | Pages 303-314
Technical Paper | doi.org/10.13182/NSE89-A23620
Mixed Convection in Parallel Channels with Application to the Liquid-Metal Reactor Concept
Victor Iannello, Neil E. Todreas
Nuclear Science and Engineering | Volume 101 | Number 4 | April 1989 | Pages 315-329
Technical Paper | doi.org/10.13182/NSE89-A23621
The Transport Equation in General Geometry
G. C. Pomraning
Nuclear Science and Engineering | Volume 101 | Number 4 | April 1989 | Pages 330-340
Technical Paper | doi.org/10.13182/NSE89-A23622
An S2 Synthetic Acceleration Scheme for the One-Dimensional Sn Equations with Linear Discontinuous Spatial Differencing
Leonard J. Lorence, Jr., J. E. Morel, Edward W. Larsen
Nuclear Science and Engineering | Volume 101 | Number 4 | April 1989 | Pages 341-351
Technical Paper | doi.org/10.13182/NSE89-A23623
Impact of Coherent Scattering on the Spectra and Energy Deposition of Gamma Rays in Bulk Media
K. V. Subbaiah, A. Natarajan, D. V. Gopinath
Nuclear Science and Engineering | Volume 101 | Number 4 | April 1989 | Pages 352-370
Technical Paper | doi.org/10.13182/NSE89-A23624
Techniques to Quantify the Sensitivity of Deterministic Model Uncertainties
T. Ishigami, E. Cazzoli, M. Khatib-Rahbar, +, S. D. Unwin†
Nuclear Science and Engineering | Volume 101 | Number 4 | April 1989 | Pages 371-383
Technical Paper | doi.org/10.13182/NSE89-A23625
Calculation of the Thermal Disadvantage Factor in a Heterogeneous Slab Cell
A. M. Abdallah
Nuclear Science and Engineering | Volume 101 | Number 4 | April 1989 | Pages 384-388
Technical Note | doi.org/10.13182/NSE89-A23626
