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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.
M. M. R. Williams, J. M. Kallfelz
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 416-419
Technical Note | doi.org/10.13182/NSE78-A27170
Articles are hosted by Taylor and Francis Online.
An analysis is made of the accuracy of the buckling approximation for the transverse leakage, used in various one- and two-dimensional transport theory computer codes. We find that the resulting approximate integro-differential form of the transport equation is not suitable for calculating accurate values of the angle-dependent flux for any case where transverse leakage has an appreciable effect on the solution. We have taken four problems, namely, critical equation, pulsed neutron and diffusion length problems, and extrapolated endpoints, and have solved them exactly using an equation derived in an earlier paper; we then solve the same problem by means of the buckling equation. In all cases, important deviations are noted that restrict the use of the buckling approximation.