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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.
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
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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Serbia lifts nuclear moratorium after 35 years
Serbia’s National Assembly has approved legislation that overturns the nation’s decades-old moratorium on nuclear power plants as the nation looks to reduce pollution.
Minister of mining and energy Dubravka Đedović Handanović posted on social media after the November 27 vote, “History has been written today. Many will inherit what has been done today!”
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The 10B(n,0)7Li and 10B(n,1)7Li Alpha-Particle Angular Distributions for En < 1 MeV
F.-J. Hambsch, I. Ruskov
Nuclear Science and Engineering | Volume 163 | Number 1 | September 2009 | Pages 1-16
Technical Paper | doi.org/10.13182/NSE09-1
Impact of New Gadolinium Cross Sections on Reaction Rate Distributions in 10 × 10 BWR Assemblies
G. Perret, M. F. Murphy, F. Jatuff, J-Ch. Sublet, O. Bouland, R. Chawla
Nuclear Science and Engineering | Volume 163 | Number 1 | September 2009 | Pages 17-25
Technical Paper | doi.org/10.13182/NSE08-55
Isotopic Signatures of Weapon-Grade Plutonium from Dedicated Natural Uranium-Fueled Production Reactors and Their Relevance for Nuclear Forensic Analysis
Alexander Glaser
Nuclear Science and Engineering | Volume 163 | Number 1 | September 2009 | Pages 26-33
Technical Paper | doi.org/10.13182/NSE163-26
A Wavelet-Based Finite Element Method for the Self-Shielding Issue in Neutron Transport
R. Le Tellier, D. Fournier, J. M. Ruggieri
Nuclear Science and Engineering | Volume 163 | Number 1 | September 2009 | Pages 34-55
Technical Paper | doi.org/10.13182/NSE163-34
On the Convergence of DGFEM Applied to the Discrete Ordinates Transport Equation for Structured and Unstructured Triangular Meshes
Yaqi Wang, Jean C. Ragusa
Nuclear Science and Engineering | Volume 163 | Number 1 | September 2009 | Pages 56-72
Technical Paper | doi.org/10.13182/NSE08-72
Surface and Volume Integrals of Uncollided Adjoint Fluxes and Forward-Adjoint Flux Products
Jeffrey A. Favorite, Keith C. Bledsoe, David I. Ketcheson
Nuclear Science and Engineering | Volume 163 | Number 1 | September 2009 | Pages 73-84
Technical Paper | doi.org/10.13182/NSE163-73
Spreading of Collimated Particle Beams Within a Generalized Fokker-Planck Diffusion Description
R. Nyqvist, D. Anderson, M. Lisak
Nuclear Science and Engineering | Volume 163 | Number 1 | September 2009 | Pages 85-90
Technical Note | doi.org/10.13182/NSE163-85
Step-Refined On-the-Fly Convergence Diagnostics of Monte Carlo Fission Source Distribution
Taro Ueki
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 99-117
Technical Paper | doi.org/10.13182/NSE163-99
Development of a Three-Dimensional Time-Dependent Calculation Scheme for Molten Salt Reactors and Validation of the Measurement Data of the Molten Salt Reactor Experiment
J. Kópházi, D. Lathouwers, J. L. Kloosterman
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 118-131
Technical Paper | doi.org/10.13182/NSE163-118
Multiphysics Analysis of Spherical Fast Burst Reactors
Samet Y. Kadioglu, Dana A. Knoll, Cassiano de Oliveira
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 132-143
Technical Paper | doi.org/10.13182/NSE09-07
Projected Predictor-Corrector Method for Lattice Physics Burnup Calculations
Akio Yamamoto, Masahiro Tatsumi, Naoki Sugimura
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 144-151
Technical Paper | doi.org/10.13182/NSE08-80
A Three-Scale Expansion Solution for a Time-Dependent P1 Neutron Transport Problem with External Source
B. Merk, F. P. Weiß
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 152-174
Technical Paper | doi.org/10.13182/NSE163-152
Measurement of 67Zn(n,p)67Cu, 92Mo(n,p)92mNb, and 98Mo(n,)99Mo Reaction Cross Sections at Incident Neutron Energies of En = 1.6 and 3.7 MeV
Megha Bhike, A. Saxena, B. J. Roy, R. K. Choudhury, S. Kailas, S. Ganesan
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 175-182
Technical Paper | doi.org/10.13182/NSE163-175
Optimization of Spent Nuclear Fuel Filling in Canisters for Deep Repository
Gasper Zerovnik, Luka Snoj, Matjaz Ravnik
Nuclear Science and Engineering | Volume 163 | Number 2 | October 2009 | Pages 183-190
Technical Paper | doi.org/10.13182/NSE163-183
Adaptive Partial-Current Discrete Ordinates Radiation Transport with Distribution Iteration: An Alternative to Source Iteration
Kirk Mathews, James Dishaw, Nicholas Wager, Nicholas Prins
Nuclear Science and Engineering | Volume 163 | Number 3 | November 2009 | Pages 191-214
Technical Paper | doi.org/10.13182/NSE163-191
Actinide Transmutation in PWRs Using CONFU Assemblies
M. Visosky, Y. Shatilla, P. Hejzlar, M. S. Kazimi
Nuclear Science and Engineering | Volume 163 | Number 3 | November 2009 | Pages 215-242
Technical Paper | doi.org/10.13182/NSE193-215
On the Diffusion Coefficients for Reactor Physics Applications
Justin M. Pounders, Farzad Rahnema
Nuclear Science and Engineering | Volume 163 | Number 3 | November 2009 | Pages 243-262
Technical Paper | doi.org/10.13182/NSE163-243
Use of a New Boundary Condition in Computational Neutron Transport
R. S. Modak, Anurag Gupta
Nuclear Science and Engineering | Volume 163 | Number 3 | November 2009 | Pages 263-271
Technical Paper | doi.org/10.13182/NSE163-263
Double-Differential Neutron Emission Cross-Section Measurements of 6Li and 7Li at Incident Neutron Energies of 8.17 and 10.27 MeV
Guochang Chen, Xichao Ruan, Zuying Zhou, Jingshang Zhang, Bujia Qi, Xia Li, Hanxiong Huang, Hongqing Tang, Qiping Zhong, Jing Jiang, Biao Xin, Jie Bao, Lin Chen
Nuclear Science and Engineering | Volume 163 | Number 3 | November 2009 | Pages 272-284
Technical Paper | doi.org/10.13182/NSE163-272
Subcritical Noise Measurements with a Nickel-Reflected Plutonium Sphere
Jesson D. Hutchinson, John D. Bess
Nuclear Science and Engineering | Volume 163 | Number 3 | November 2009 | Pages 285-290
Technical Paper | doi.org/10.13182/NSE163-285
