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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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
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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.
M. E. Sawan, I. N. Sviatoslavsky
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 1141-1145
Fusion Power Reactor, Economic, and Alternate Concept | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40307
Articles are hosted by Taylor and Francis Online.
The neutron yield in a D-3He reactor is much lower than that in a D-T reactor of equivalent power. Therefore, the rate of neutron damage and gas production in the first wall of D-3He reactors is lower by more than an order of magnitude. Whereas different structural materials proposed for use in commercial fusion reactors will last the reactor lifetime of 30 full power years in a D-3He reactor, frequent replacement of the first wall and blanket will be required during the lifetime of a D-T power reactor. The blanket modules may require 30 replacements depending on the material used and the maximum allowable damage level. The down time required for replacement of the first wall and blanket in a D-T reactor will impact the reactor availability and consequently the cost of electricity. It appears that a D-3He reactor should have a 10% advantage in availability over a D-T reactor.