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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
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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
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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A Global Physics Approach to Transmutation of Radioactive Nuclei
M. Salvatores, I. Slessarev, M. Uematsu
Nuclear Science and Engineering | Volume 116 | Number 1 | January 1994 | Pages 1-18
Technical Paper | doi.org/10.13182/NSE94-A21476
Measurement of Radioactivity Production for 48V 56Co, and 65Zn Via the (p,n) Sequential Reaction Processes in Titanium, Iron, and Copper Metals Associated with 14-MeV Neutron Irradiation
Y. Ikeda, C. Konno, H. Maekawa
Nuclear Science and Engineering | Volume 116 | Number 1 | January 1994 | Pages 19-27
Technical Paper | doi.org/10.13182/NSE94-A21477
Measurement of Neutron Activation Cross Sections for the 99Tc(n,p)99Mo, 99Tc(n,α)96Nb, 99Tc(n,n′α)95Nb, and“Tc(n,n′)99mTc Reactions at 13.5 and 14.8 MeV
Y. Ikeda, E. T. Cheng, C. Konno, H. Maekawa
Nuclear Science and Engineering | Volume 116 | Number 1 | January 1994 | Pages 28-34
Technical Paper | doi.org/10.13182/NSE94-A21478
A Method for Calculating Double-Differential Cross Sections of Alpha-Particle Emissions
Jingshang Zhang
Nuclear Science and Engineering | Volume 116 | Number 1 | January 1994 | Pages 35-41
Technical Paper | doi.org/10.13182/NSE93-28
Solution of the Mathematical Adjoint Equations for an Interface Current Nodal Formulation
W. S. Yang, T. A. Taiwo, H. Khalil
Nuclear Science and Engineering | Volume 116 | Number 1 | January 1994 | Pages 42-54
Technical Paper | doi.org/10.13182/NSE94-A21480
An Investigation of the Temporal Subdomain Method for Solving the Finite Element Formulation of the Space-Time Reactor Kinetics Equations
Haluk Utku, John M. Christenson
Nuclear Science and Engineering | Volume 116 | Number 1 | January 1994 | Pages 55-66
Technical Note | doi.org/10.13182/NSE94-A21481
The Reactor Noise Threshold
Gregory D. Spriggs
Nuclear Science and Engineering | Volume 116 | Number 1 | January 1994 | Pages 67-72
Technical Note | doi.org/10.13182/NSE94-A21482
A Fission-Source Acceleration Technique for Time-Dependent Even-Parity Sn Calculations
J. E. Morel, J. M. McGhee
Nuclear Science and Engineering | Volume 116 | Number 2 | February 1994 | Pages 73-85
Technical Paper | doi.org/10.13182/NSE94-A21484
Effective Diffusion Homogenization of Cross Sections for Pressurized Water Reactor Core Calculations
Nuclear Science and Engineering | Volume 116 | Number 2 | February 1994 | Pages 86-95
Technical Paper | doi.org/10.13182/NSE94-A21485
A Probabilistic Method for Evaluating Reactivity Feedbacks and Its Application to Experimental Breeder Reactor II
R. W. Schaefer
Nuclear Science and Engineering | Volume 116 | Number 2 | February 1994 | Pages 96-112
Technical Paper | doi.org/10.13182/NSE94-A21486
A Monte Carlo Variance Reduction Approach for Non-Boltzmann Tallies
Thomas E. Booth
Nuclear Science and Engineering | Volume 116 | Number 2 | February 1994 | Pages 113-124
Technical Paper | doi.org/10.13182/NSE94-A21487
Excitation Functions of Neutron Threshold Reactions on Some Isotopes of Germanium, Arsenic, and Selenium in the 6.3- to 14.7-MeV Energy Range
I. Birn, S. M. Qaim
Nuclear Science and Engineering | Volume 116 | Number 2 | February 1994 | Pages 125-137
Technical Paper | doi.org/10.13182/NSE94-A21488
Measurements of the Modified Conversion Ratio by Gamma-Ray Spectrometry of Fuel Rods for Water-Moderated UO2 Cores
Ken Nakajima, Masanori Akai, Takenori Suzaki
Nuclear Science and Engineering | Volume 116 | Number 2 | February 1994 | Pages 138-146
Technical Paper | doi.org/10.13182/NSE94-A21489
Vectorization Methods Development for a New Version of the KENO-V.a Criticality Safety Code
D. F. Hollenbach, L. M. Petri, H. L. Dodds
Nuclear Science and Engineering | Volume 116 | Number 3 | March 1994 | Pages 147-164
Technical Paper | doi.org/10.13182/NSE94-A19810
A New Approach of Analytic Basis Function Expansion to Neutron Diffusion Nodal Calculation
Jae Man Noh, Nam Zin Cho
Nuclear Science and Engineering | Volume 116 | Number 3 | March 1994 | Pages 165-180
Technical Paper | doi.org/10.13182/NSE94-A19811
Fast Shutdown Margin Calculation Using Perturbation Theory with Regionwise Flux Expansion
Jeng-Ming Fang, Yen-Wan H. Liu, Horng-Kuang Liu, Pin-Wu Kao, Jing-Tong Yang
Nuclear Science and Engineering | Volume 116 | Number 3 | March 1994 | Pages 181-204
Technical Paper | doi.org/10.13182/NSE94-A19812
A Study on Applicability of Decay Ratio Estimation in a Pressurized Water Reactor
G. Por, J. Runkel
Nuclear Science and Engineering | Volume 116 | Number 3 | March 1994 | Pages 205-212
Technical Paper | doi.org/10.13182/NSE94-A19813
Statistical Model Calculation of the 237U Fission Cross Section
J. P. Lestone, A. Gavron
Nuclear Science and Engineering | Volume 116 | Number 3 | March 1994 | Pages 213-217
Technical Paper | doi.org/10.13182/NSE94-A19814
Study of Photon Attenuation Coefficients of Some Multielement Materials
G. S. Bhandal, K. Singh
Nuclear Science and Engineering | Volume 116 | Number 3 | March 1994 | Pages 218-222
Technical Note | doi.org/10.13182/NSE94-A19815
Stability, Accuracy, and Convergence of the Numerical Methods in RELAP5/MOD3
A. S.-L. Shieh, R. Krishnamurthy, V. H. Ransom
Nuclear Science and Engineering | Volume 116 | Number 4 | April 1994 | Pages 227-244
Technical Paper | doi.org/10.13182/NSE94-A18984
Rod Bundle Thermal-Hydraulic and Melt Progression Analysis of CORA Severe Fuel Damage Experiments
Kune Y. Suh
Nuclear Science and Engineering | Volume 116 | Number 4 | April 1994 | Pages 245-268
Technical Paper | doi.org/10.13182/NSE94-A18985
Comparison of Scientific Computing Platforms for MCNP4A Monte Carlo Calculations
J. S. Hendricks, R. C. Brockhoff
Nuclear Science and Engineering | Volume 116 | Number 4 | April 1994 | Pages 269-277
Technical Paper | doi.org/10.13182/NSE94-A18986
Neutron Penetration Through Iron and Concrete Shields with the Use of 22.0- and 32.5-MeV Quasi-Monoenergetic Sources
Toshio Ishikawa
Nuclear Science and Engineering | Volume 116 | Number 4 | April 1994 | Pages 278-290
Technical Paper | doi.org/10.13182/NSE94-A18987
Space Proton Transport in One Dimension
Stanley L. Lamkin and Govind S. Khandelwal, Judy L. Shinn, John W. Wilson
Nuclear Science and Engineering | Volume 116 | Number 4 | April 1994 | Pages 291-299
Technical Paper | doi.org/10.13182/NSE94-A18988
A New Approach to Core-Reflector Boundary Conditions for Nodal Reactor Computations
Hyung Kook Joo, Chang Hyo Kim, Jae Man Noh, Si-Hwan Kim
Nuclear Science and Engineering | Volume 116 | Number 4 | April 1994 | Pages 300-312
Technical Paper | doi.org/10.13182/NSE94-A18989
Detecting Faults in a Nuclear Power Plant by Using Dynamic Node Architecture Artificial Neural Networks
Anujit Basu, Eric B. Bartlett
Nuclear Science and Engineering | Volume 116 | Number 4 | April 1994 | Pages 313-325
Technical Paper | doi.org/10.13182/NSE94-A18990
