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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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Nuclear Science and Engineering
May 2025
Nuclear Technology
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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Radial Moment Calculations of Coupled Electron-Photon Beams
Brian C. Franke, Edward W. Larsen
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 1-22
Technical Paper | doi.org/10.13182/NSE02-A2242
Treatment of Boundary Conditions in Trajectory-Based Deterministic Transport Methods
Richard Sanchez, Li Mao, Simone Santandrea
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 23-50
Technical Paper | doi.org/10.13182/NSE140-23
An Asymptotic Study of Discretized Transport Equations in the Fokker-Planck Limit
Shawn D. Pautz, Marvin L. Adams
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 51-69
Technical Paper | doi.org/10.13182/NSE02-A2244
Application of Neutron Dosimetry Measurements in the Determination of Reactor Pressure Vessel Fluence
John F. Carew, Kai Hu
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 70-85
Technical Paper | doi.org/10.13182/NSE02-A2245
Fast Neutron-Induced Emission of Light Charged Particles on Aluminum (En = 25 to 55 MeV)
S. Benck, I. Slypen, J.-P. Meulders, V. Corcalciuc, M. B. Chadwick
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 86-95
Technical Paper | doi.org/10.13182/NSE02-A2246
Studies on Photon Interaction Around the K-Edge of Some Elements
M. L. Mallikarjuna, S. B. Appaji Gowda, S. Krishnaveni, R. Gowda, T. K. Umesh
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 96-102
Technical Paper | doi.org/10.13182/NSE02-A2247
Nuclear Model Calculations for the Excitation Functions of Neutron-Induced Reactions on 58Ni in the Energy Range up to 20 MeV
K. Gul
Nuclear Science and Engineering | Volume 140 | Number 1 | January 2002 | Pages 103-110
Technical Paper | doi.org/10.13182/NSE02-A2248
An Algorithm for Parallel Sn Sweeps on Unstructured Meshes
Shawn D. Pautz
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 111-136
Technical Paper | doi.org/10.13182/NSE02-1
Unified Nodal Method Formulation for Analytic Function Expansion Nodal Method Solution to Two-Group Diffusion Equations in Rectangular Geometry
Hyun Chul Lee, Chang Hyo Kim
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 137-151
Technical Paper | doi.org/10.13182/NSE02-A2250
Three-Dimensional Modeling of a Steam-Line Break in a Boiling Water Reactor
Hernan Tinoco
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 152-164
Technical Paper | doi.org/10.13182/NSE02-A2251
Fluid Mechanics of Taylor Bubbles and Slug Flows in Vertical Channels
Henryk Anglart, Michael Z. Podowski
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 165-171
Technical Paper | doi.org/10.13182/NSE02-A2252
Thermohydraulics Oscillations and Numerical Integration
D. Ginestar, G. Verdú, J. March-Leuba
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 172-180
Technical Paper | doi.org/10.13182/NSE02-A2253
Implementation of a Two-Phase Boiling Model into the RELAP5/MOD2 Computer Code to Predict Void Distribution in Low-Pressure Subcooled Boiling Flows
G. H. Yeoh, J. Y. Tu
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 181-188
Technical Note | doi.org/10.13182/NSE02-A2254
Neutron Flux Perturbations due to Infinite Plane Absorbers IV: The Exponential Flux Revisited
M. M. R. Williams
Nuclear Science and Engineering | Volume 140 | Number 2 | February 2002 | Pages 189-194
Technical Note | doi.org/10.13182/NSE02-A2255
High-Resolution Cross-Section Measurements for Production of the 0.478-MeV Gamma Ray from the 9Be(n,x)7Li Reaction for Neutron Energies Between 12 and 200 MeV with Insight into the 10Be Level Scheme
R. O. Nelson, A. Michaudon
Nuclear Science and Engineering | Volume 140 | Number 3 | March 2002 | Pages 195-204
Technical Paper | doi.org/10.13182/NSE02-A2256
Studies on Plutonium Burning in the Prototype Fast Breeder Reactor Monju
Udo Wehmann, Hidehito Kinjo, Takeshi Kageyama
Nuclear Science and Engineering | Volume 140 | Number 3 | March 2002 | Pages 205-222
Technical Paper | doi.org/10.13182/NSE02-A2257
The Fission Converter-Based Epithermal Neutron Irradiation Facility at the Massachusetts Institute of Technology Reactor
O. K. Harling, K. J. Riley, T. H. Newton, B. A. Wilson, J. A. Bernard, L-W. Hu, E. J. Fonteneau, P. T. Menadier, S. J. Ali, B. Sutharshan, G. E. Kohse, Y. Ostrovsky, P. W. Stahle, P. J. Binns, W. S. Kiger III, P. M. Busse
Nuclear Science and Engineering | Volume 140 | Number 3 | March 2002 | Pages 223-240
Technical Paper | doi.org/10.13182/NSE02-A2258
Analysis of Unplated Subcritical Experiments Using Fresh Fuel Assemblies
Michelle Pitts, Farzad Rahnema
Nuclear Science and Engineering | Volume 140 | Number 3 | March 2002 | Pages 241-266
Technical Paper | doi.org/10.13182/NSE02-A2259
Kinetics Calculation Under Space-Dependent Feedback in Analytic Function Expansion Nodal Method via Solution Decomposition and Galerkin Scheme
Do Sam Kim, Nam Zin Cho
Nuclear Science and Engineering | Volume 140 | Number 3 | March 2002 | Pages 267-284
Technical Paper | doi.org/10.13182/NSE02-A2260
High-Order Boundary Condition Perturbation Theory for the Neutron Transport Equation
Michael Scott McKinley, Farzad Rahnema
Nuclear Science and Engineering | Volume 140 | Number 3 | March 2002 | Pages 285-294
Technical Paper | doi.org/10.13182/NSE02-A2261
