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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
R. C. Erdmann, H. Lurie
Nuclear Science and Engineering | Volume 28 | Number 2 | May 1967 | Pages 198-202
Technical Paper | doi.org/10.13182/NSE67-A17469
Articles are hosted by Taylor and Francis Online.
Using an exact transport solution, numerical calculations of interface flux and current are made for a plane burst of neutrons introduced at the boundary separating two semi-infinite media. Asymptotic flux expressions for large time at the interface are also presented, and these have the exponential dependence given by diffusion theory. Following the neutron burst, the interface current is found to change directions once, at most. The magnitude of the interface current is shown to depend initially on the difference in scattering cross sections of the half-spaces and asymptotically on the difference in absorption cross sections. In the special case of identical half-spaces, diffusion theory yields a more accurate representation of the flux than does P1 theory, although for long times both approximate solutions rapidly approach the exact result.