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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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Analysis of Ray-Effect Mitigation Techniques
J. E. Morel, T. A. Wareing, R. B. Lowrie, D. K. Parsons
Nuclear Science and Engineering | Volume 144 | Number 1 | May 2003 | Pages 1-22
Technical Paper | doi.org/10.13182/NSE01-48
Analytic Coarse-Mesh Finite-Difference Method Generalized for Heterogeneous Multidimensional Two-Group Diffusion Calculations
Nuria García-Herranz, Oscar Cabellos, José M. Aragonés, Carol Ahnert
Nuclear Science and Engineering | Volume 144 | Number 1 | May 2003 | Pages 23-35
Technical Paper | doi.org/10.13182/NSE03-A2340
A Finite Subelement Generalization of the Variational Nodal Method
M. A. Smith, N. Tsoulfanidis, E. E. Lewis, G. Palmiotti, T. A. Taiwo
Nuclear Science and Engineering | Volume 144 | Number 1 | May 2003 | Pages 36-46
Technical Paper | doi.org/10.13182/NSE144-36
The Reactivity Temperature Coefficient Analysis in Light Water Moderated UO2 and UO2-PuO2 Lattices
L. Erradi, A. Santamarina, O. Litaize
Nuclear Science and Engineering | Volume 144 | Number 1 | May 2003 | Pages 47-73
Technical Paper | doi.org/10.13182/NSE144-47
Scaling and Parametric Studies of Condensation Oscillation in an In-Containment Refueling Water Storage Tank
Jun Hyung Lee, Hee Cheon No
Nuclear Science and Engineering | Volume 144 | Number 1 | May 2003 | Pages 74-85
Technical Paper | doi.org/10.13182/NSE03-A2343
Scattering of Intermediate-Energy Neutrons from Nuclei and the Ramsauer Hypothesis
Mofazzal Azam, Rajesh S. Gowda
Nuclear Science and Engineering | Volume 144 | Number 1 | May 2003 | Pages 86-93
Technical Paper | doi.org/10.13182/NSE03-A2344
Neutron Capture Cross-Section Measurement of Rhodium in the Energy Region from 0.003 eV to 80 keV by Linac Time-of-Flight Method
Samyol Lee, Shuji Yamamoto, Katsuhei Kobayashi, Guinyun Kim, Jonghwa Chang
Nuclear Science and Engineering | Volume 144 | Number 1 | May 2003 | Pages 94-107
Technical Paper | doi.org/10.13182/NSE03-A2345
Angular Distribution and Cross-Section Measurements for 64Zn(n,)61Ni Reaction at 5.0, 5.7, and 6.5 MeV
Jing Yuan, Zemin Chen, Guoyou Tang, Guohui Zhang, Jinxiang Chen, Zhaomin Shi, Yu. M. Gledenov, M. Sedysheva, G. Khuukhenkhuu
Nuclear Science and Engineering | Volume 144 | Number 1 | May 2003 | Pages 108-112
Technical Paper | doi.org/10.13182/NSE03-A2346
Validation of Minor Actinide Cross Sections by Studying Samples Irradiated for 492 Days at the Dounreay Prototype Fast Reactor - I: Radiochemical Analysis
N. Shinohara, N. Kohno, Y. Nakahara, K. Tsujimoto, T. Sakurai, T. Mukaiyama, S. Raman
Nuclear Science and Engineering | Volume 144 | Number 2 | June 2003 | Pages 115-128
Technical Paper | doi.org/10.13182/NSE03-A2347
Validation of Minor Actinide Cross Sections by Studying Samples Irradiated for 492 Days at the Dounreay Prototype Fast Reactor - II: Burnup Calculations
K. Tsujimoto, N. Kohno, N. Shinohara, T. Sakurai, Y. Nakahara, T. Mukaiyama, S. Raman
Nuclear Science and Engineering | Volume 144 | Number 2 | June 2003 | Pages 129-141
Technical Paper | doi.org/10.13182/NSE03-A2348
Precise Validation of Database (n,) Cross Sections Using a Lead-Slowing-Down Spectrometer and Simulation from 0.1 eV to 30 keV: Methodology and Data for a Few Elements
L. Perrot, A. Billebaud, R. Brissot, A. Giorni, D. Heuer, J.-M. Loiseaux, O. Méplan, J.-B. Viano
Nuclear Science and Engineering | Volume 144 | Number 2 | June 2003 | Pages 142-156
Technical Paper | doi.org/10.13182/NSE03-A2349
Photonuclear Physics in Radiation Transport—I: Cross Sections and Spectra
M. B. Chadwick, P. G. Young, R. E. MacFarlane, M. C. White, R. C. Little
Nuclear Science and Engineering | Volume 144 | Number 2 | June 2003 | Pages 157-173
Technical Paper | doi.org/10.13182/NSE144-157
Photonuclear Physics in Radiation Transport—II: Implementation
M. C. White, R. C. Little, M. B. Chadwick, P. G. Young, R. E. MacFarlane
Nuclear Science and Engineering | Volume 144 | Number 2 | June 2003 | Pages 174-189
Technical Paper | doi.org/10.13182/NSE144-174
Criticality and Reactivity Measurement Method for Nuclear Material Control and Accountability
N. N. Ponomarev-Stepnoi, Y. S. Glushkov, V. P. Garin, G. V. Kompaniets, V. I. Nosov, R. G. Sanchez, R. R. Paternoster, S. P. Gary
Nuclear Science and Engineering | Volume 144 | Number 3 | July 2003 | Pages 191-199
Technical Paper | doi.org/10.13182/NSE03-A2352
A Numerical Method for Computing Collision, Escape, and Transmission Probabilities in Three Dimensions
R. D. M. Garcia
Nuclear Science and Engineering | Volume 144 | Number 3 | July 2003 | Pages 200-210
Technical Paper | doi.org/10.13182/NSE03-A2353
Effects of Nuclear Data Library on BFS and ZPPR keff Analysis Results
Gennadi Manturov
Nuclear Science and Engineering | Volume 144 | Number 3 | July 2003 | Pages 211-218
Technical Paper | doi.org/10.13182/NSE03-A2354
The Fragment Distribution of Nb, Au, and Pb from Proton-Induced Reactions with Energies Ranging from 100 MeV to 3 GeV
S. Fan, J. Rong, H. Zhang, Z. Zhao
Nuclear Science and Engineering | Volume 144 | Number 3 | July 2003 | Pages 219-226
Technical Paper | doi.org/10.13182/NSE03-A2355
Characterization of a Source Importance Function in an Accelerator-Driven System
Yonghee Kim, Won Seok Park, Chang Kue Park
Nuclear Science and Engineering | Volume 144 | Number 3 | July 2003 | Pages 227-241
Technical Paper | doi.org/10.13182/NSE03-A2356
An Investigation of Power Stabilization and Space-Dependent Dynamics of a Nuclear Fluidized-Bed Reactor
Christopher C. Pain, Matthew D. Eaton, Jefferson L. M. A. Gomes, Cassiano R. E. de Oliveira, Adrian P. Umpleby, Kemal Ziver, Ron T. Ackroyd, Bryan Miles, Antony J. H. Goddard, H. van Dam, T. H. J. J. van der Hagen, D. Lathouwers
Nuclear Science and Engineering | Volume 144 | Number 3 | July 2003 | Pages 242-257
Technical Note | doi.org/10.13182/NSE03-A2357
Dynamic Adsorption of Noble Gases
Dwight Underhill
Nuclear Science and Engineering | Volume 144 | Number 3 | July 2003 | Pages 258-260
Technical Note | doi.org/10.13182/NSE03-A2358
