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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
D. D. Ryutov, Y. C. F. Thio
Fusion Science and Technology | Volume 49 | Number 1 | January 2006 | Pages 39-55
Technical Paper | doi.org/10.13182/FST06-A1084
Articles are hosted by Taylor and Francis Online.
One of the challenging problems of magnetized target fusion (MTF) is developing ways to transport energy to the target situated at a distance far enough from the energy source so as to prevent damage to the permanent parts of the source. Several schemes were considered in the past, including the use of particle beams coupled with the inverse diode, mechanical projectiles in combination with magnetocompressional generators, and the plasma liner. In this paper, a possible modification of the original concept of the plasma liner (by Thio et al.) is described. The modification consists of creating a thin, higher-density shell made of a high-Z plasma and accelerating it onto an MTF target by the thermal pressure of hydrogen plasma with a temperature of ~10 eV. We discuss constraints on the parameters of this system and evaluate the convergence ratio that can be expected.