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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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.
D. P. Brown, W. G. Spear
Nuclear Technology | Volume 23 | Number 1 | July 1974 | Pages 87-93
Technical Paper | Instrument | doi.org/10.13182/NT74-A31436
Articles are hosted by Taylor and Francis Online.
A detector using a gas-flow technique to measure the in-core fast neutron flux was designed, developed, and experimentally tested. Based on the 9Be(n,α)6He reaction of neutrons with beryllium, the method uses a flowing gas (helium) to bring the 6He beta emitter to an ex-vessel beta detector to achieve measurements independent of the gamma irradiation of the in-vessel neutron detector. In tests at the TRIGA reactor of Washington State University, the system demonstrated a fast neutron sensitivity of 3.7 × 10−10 counts/sec per n/(cm2 sec). Thus, using appropriate counting techniques, the technique could have an operational range of 109 to 1016n/(cm2 sec).