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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.
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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.
Osman Yasar, Gregory A. Moses, Robert R. Peterson
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 669-672
Inertial Fusion | doi.org/10.13182/FST91-A29421
Articles are hosted by Taylor and Francis Online.
One method of propagating light ions from beam generating diodes to ICF targets in a fusion reactor is to use laser-guided plasma discharge channels to magnetically guide the ions. Earlier studies of different cavity gases (argon, nitrogen, helium) for the LIBRA reactor study indicated that the lower atomic number gases (helium) were most suitable for plasma channel formation. We found unacceptable channel expansion due to radiative transfer where the radiation transport was calculated with a multigroup diffusion computer code. A new set of simulations using a newly developed adaptive-grid radiation magnetohydrodynamics scheme with a multigroup discrete ordinates radiation transport method has led to lower absorption and emission by such thin plasmas. Application of the new scheme to LIBRA thus shows the feasibility of using argon and nitrogen as well for the channel plasma. Higher atomic number gases more strongly attenuate the x-rays coming from the target explosion. Also, by using an adaptive grid, the new scheme provides better accuracy and resolution where it is needed in the channel. The discharge current required to form the channel is found to be 70 kA as opposed to 100 kA predicted by earlier calculations. This will have the effect of reducing the required discharge voltage and thus will ease the problem of electrical breakdown between the channel and the target chamber wall.