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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.
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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
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.
B. T. Rearden
Nuclear Science and Engineering | Volume 146 | Number 3 | March 2004 | Pages 367-382
Technical Paper | doi.org/10.13182/NSE03-03
Articles are hosted by Taylor and Francis Online.
Methodologies to calculate adjoint-based first-order-linear perturbation theory sensitivity coefficients with multigroup Monte Carlo methods are developed, implemented, and tested in this paper. These techniques can quickly produce sensitivity coefficients for all nuclides and reaction types for each region of a system model. Monte Carlo techniques have been developed to calculate the neutron flux moments and/or angular fluxes necessary for the generation of the scattering terms of the sensitivity coefficients.The Tools for Sensitivity and Uncertainty Analysis Methodology Implementation in three dimensions (TSUNAMI-3D) control module has been written for the Standardized Computer Analyses for Licensing Evaluation (SCALE) code system implementing this methodology. TSUNAMI-3D performs automated multigroup cross-section processing and then generates the forward and adjoint neutron fluxes with an enhanced version of the KENO V.a Monte Carlo code that implements the flux moment and angular flux calculational techniques. Sensitivity coefficients are generated with the newly developed Sensitivity Analysis Module for SCALE (SAMS). Results generated with TSUNAMI-3D compare favorably with results generated with direct perturbation techniques.
