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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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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.
R. W. Moir, R. H. Bulmer, T. K. Fowler, T. D. Rognlien, M. Z. Youssef
Fusion Science and Technology | Volume 44 | Number 2 | September 2003 | Pages 317-326
Technical Paper | Fusion Energy - Chamber Technology | doi.org/10.13182/FST03-A354
Articles are hosted by Taylor and Francis Online.
A power plant based on a spheromak device using liquid walls is analyzed. We assume a spheromak configuration can be made and sustained by a steady plasma gun current, which injects particles, current and magnetic field, i.e., helicity injection, which are transported into the core region. The magnetic configuration is evaluated with an axisymmetric freeboundary equilibrium code, where the current profile is tailored to support an average beta of 10%. An injection current of 100 kA (125 MW of gun power) sustains the toroidal current of 40 MA. The magnetic flux linking the gun is 1/1000th of the flux in the spheromak. The geometry allows a flow of liquid, either molten salt, (flibe-Li2BeF4 or flinabe-LiNaBeF4), or liquid metal such as SnLi, which protects most of the walls and structures from damage arising from neutrons and plasma particles. The free surface between the liquid and the burning plasma is heated primarily by bremsstrahlung, line radiation, and some by neutrons. The temperature of the free surface of the liquid is calculated and then the evaporation rate is estimated from vapor-pressure data. The impurity concentration in the burning plasma, about 0.8% fluorine, is limited to that giving a 20% reduction in the fusion power. The divertor power density of 620 MW/m2 is handled by high-speed (100 m/s) liquid jets. Calculations show the tritium breeding is adequate with enriched 6Li, and a design is given for the walls not covered by flowing liquid (~15% of the total). We identified a number of problem areas needing further study to make the design more self-consistent and workable, including lowering the divertor power density by expanding the flux tube size.
