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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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
Fusion Science and Technology
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.
G. Velarde, J.M. Aragonés, M.C. Gonzalez, P. Hernén, J.J. Honrubia J.L. Hortal, J.M. Martínez-Val, E, Mínguez, J.L. Ocaña, J.M. Perlado, J.M. Santolaya, J. Sanz
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1850-1855
Inertial Confinement Fusion Reactor | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40030
Articles are hosted by Taylor and Francis Online.
This article discusses the effect of different potential spectra of neutrons leaking from an inertial confinement fusion (ICF) pellet on integral parameters characterizing the blanket performance. We have compared time dependent and steady state neutron calculations to determine the neutron and gamma spectra from the target. Results show, that assuming a fuel burnup-average ρR parameter,<ρR>b, in the steady state method, realistic spectra can be obtained. The influence of the fuel <ρR>b, ρΔR pusher parameter as well as that of the gammas exploding from the target, on the chamber response has been analyzed.
