ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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 Technology
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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. Anderson
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 428-430
Technical Note | Fission Reactor | doi.org/10.13182/NT81-A32717
Articles are hosted by Taylor and Francis Online.
Neutron yields of 239Pu-Be(α,n) sources are increasing due to the buildup of 241 Am, an alpha emitter, from the beta decay of 241 Pu. The yields and heat outputs of four sources, in which PuBe13 was formed during fabrication, have been followed for several years. Rates of increase in neutron yields at t = 0 vary from 0.3 to 1.9%/yr for initial 241 Pu contents from 0.10 to 0.70%. For three of these sources the increase in neutron yield follows the radioactive decay of the constituents. For the fourth, the increase in neutron yield is greater than expected. A possible explanation is offered.