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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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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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Experimental Determination of the Ratio of 238U Capture to 235U Fission in LEU-HTR Pebble-Bed Configurations
O. Köberl, R. Seiler, R. Chawla
Nuclear Science and Engineering | Volume 146 | Number 1 | January 2004 | Pages 1-12
Technical Paper | doi.org/10.13182/NSE04-A2391
Impact of Nuclear Data Uncertainties on Transmutation of Actinides in Accelerator-Driven Assemblies
G. Aliberti, G. Palmiotti, M. Salvatores, C. G. Stenberg
Nuclear Science and Engineering | Volume 146 | Number 1 | January 2004 | Pages 13-50
Technical Paper | doi.org/10.13182/NSE02-94
Using the Schwinger Variational Functional for the Solution of Inverse Transport Problems
Jeffrey A. Favorite
Nuclear Science and Engineering | Volume 146 | Number 1 | January 2004 | Pages 51-70
Technical Paper | doi.org/10.13182/NSE02-96
Calculating Nuclear Power Plant Vulnerability Using Integrated Geometry and Event/Fault-Tree Models
Douglas E. Peplow, C. David Sulfredge, Robert L. Sanders, Robert H. Morris, Todd A. Hann
Nuclear Science and Engineering | Volume 146 | Number 1 | January 2004 | Pages 71-87
Technical Paper | doi.org/10.13182/NSE04-A2394
An Order Coding Genetic Algorithm to Optimize Fuel Reloads in a Nuclear Boiling Water Reactor
Juan José Ortiz, Ignacio Requena
Nuclear Science and Engineering | Volume 146 | Number 1 | January 2004 | Pages 88-98
Technical Paper | doi.org/10.13182/NSE04-A2395
Slowing-Down Dynamics of Fast Particles in Plasmas via the Fokker-Planck Equation
D. Anderson, M. Lisak, F. Andersson, T. Fülöp
Nuclear Science and Engineering | Volume 146 | Number 1 | January 2004 | Pages 99-105
Technical Paper | doi.org/10.13182/NSE04-A2396
Calculation and Analysis of n + 112,114-120,122,124,natSn Reactions
Yinlu Han
Nuclear Science and Engineering | Volume 146 | Number 1 | January 2004 | Pages 106-119
Technical Paper | doi.org/10.13182/NSE04-A2397
Variational Variance Reduction for Monte Carlo Eigenvalue and Eigenfunction Problems
Jeffery D. Densmore, Edward W. Larsen
Nuclear Science and Engineering | Volume 146 | Number 2 | February 2004 | Pages 121-140
Technical Paper | doi.org/10.13182/NSE04-A2398
An Integral Form of the Variational Nodal Method
M. A. Smith, G. Palmiotti, E. E. Lewis, N. Tsoulfanidis
Nuclear Science and Engineering | Volume 146 | Number 2 | February 2004 | Pages 141-151
Technical Paper | doi.org/10.13182/NSE146-141
Conditions for a Minimum Critical Mass in a Nuclear Reactor and Considerations on Goertzel's Theorem in Transport Theory
M. M. R. Williams
Nuclear Science and Engineering | Volume 146 | Number 2 | February 2004 | Pages 152-175
Technical Paper | doi.org/10.13182/NSE04-A2400
A Hybrid Nodal Diffusion/SP3 Method Using One-Node Coarse-Mesh Finite Difference Formulation
Chang-Ho Lee, Thomas J. Downar
Nuclear Science and Engineering | Volume 146 | Number 2 | February 2004 | Pages 176-187
Technical Paper | doi.org/10.13182/NSE04-A2401
Benchmarking MCNP and WIMS/RFSP Against Measurement Data - I: Deuterium Critical Assembly
Hangbok Choi, Gyuhong Roh
Nuclear Science and Engineering | Volume 146 | Number 2 | February 2004 | Pages 188-199
Technical Paper | doi.org/10.13182/NSE04-A2402
Measurement of Differential Thick-Target Neutron Yields of C, Al, Ta, W(p,xn) Reactions for 50-MeV Protons
T. Aoki, M. Baba, S. Yonai, N. Kawata, M. Hagiwara, T. Miura, T. Nakamura
Nuclear Science and Engineering | Volume 146 | Number 2 | February 2004 | Pages 200-208
Technical Paper | doi.org/10.13182/NSE04-A2403
Neutron Capture Cross-Section Measurement of 99Tc by Linac Time-of-Flight Method and the Resonance Analysis
Katsuhei Kobayashi, Samyol Lee, Shuji Yamamoto, Toshihiko Kawano
Nuclear Science and Engineering | Volume 146 | Number 2 | February 2004 | Pages 209-220
Technical Paper | doi.org/10.13182/NSE04-A2404
Calculation of the Complete Sets of Nuclear Data for n + 92,94,96Mo below 20 MeV
Chonghai Cai
Nuclear Science and Engineering | Volume 146 | Number 2 | February 2004 | Pages 221-236
Technical Paper | doi.org/10.13182/NSE04-A2405
Investigation of the Outgoing Tritons Angular Distribution in the 9Be(n,t1)7Li* Reaction at 14.9 MeV by the Line Shape Analysis of the 0.4776-MeV Gamma Transition
Hongyu Zhou, Ping Wang, Hai Song, Fucai Wu, Fuguo Deng, Ming Hua, Yiming Yan, A. A. Pasternak
Nuclear Science and Engineering | Volume 146 | Number 2 | February 2004 | Pages 237-244
Technical Paper | doi.org/10.13182/NSE04-A2406
Accurate Relations Between the Neutron Current Densities and the Neutron Fluxes
Yigal Ronen
Nuclear Science and Engineering | Volume 146 | Number 2 | February 2004 | Pages 245-247
Technical Note | doi.org/10.13182/NSE04-A2407
BOT3P - Bologna Transport Analysis Pre-Post-Processors Version 3.0
Roberto Orsi
Nuclear Science and Engineering | Volume 146 | Number 2 | February 2004 | Pages 248-255
Technical Note | doi.org/10.13182/NSE04-A2408
Development of One-Group and Two-Group Interfacial Area Transport Equation
M. Ishii, S. Kim
Nuclear Science and Engineering | Volume 146 | Number 3 | March 2004 | Pages 257-273
Technical Paper | doi.org/10.13182/NSE01-69
Adequacy of Power-to-Mass Scaling in Simulating PWR Incident Transient for Reduced-Height, Reduced-Pressure and Full-Height, Full-Pressure Integral System Test Facilities
Tay-Jian Liu, Chien-Hsiung Lee
Nuclear Science and Engineering | Volume 146 | Number 3 | March 2004 | Pages 274-290
Technical Paper | doi.org/10.13182/NSE04-A2410
Long-Lived Fission Product Transmutation Studies
W. S. Yang, Y. Kim, R. N. Hill, T. A. Taiwo, H. S. Khalil
Nuclear Science and Engineering | Volume 146 | Number 3 | March 2004 | Pages 291-318
Technical Paper | doi.org/10.13182/NSE04-A2411
A Nodal and Finite Difference Hybrid Method for Pin-by-Pin Heterogeneous Three-Dimensional Light Water Reactor Diffusion Calculations
Deokjung Lee, Thomas J. Downar, Yonghee Kim
Nuclear Science and Engineering | Volume 146 | Number 3 | March 2004 | Pages 319-339
Technical Paper | doi.org/10.13182/NSE04-A2412
Sensitivity- and Uncertainty-Based Criticality Safety Validation Techniques
B. L. Broadhead, B. T. Rearden, C. M. Hopper, J. J. Wagschal, C. V. Parks
Nuclear Science and Engineering | Volume 146 | Number 3 | March 2004 | Pages 340-366
Technical Paper | doi.org/10.13182/NSE03-2
Perturbation Theory Eigenvalue Sensitivity Analysis with Monte Carlo Techniques
B. T. Rearden
Nuclear Science and Engineering | Volume 146 | Number 3 | March 2004 | Pages 367-382
Technical Paper | doi.org/10.13182/NSE03-03
