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U.S. Department of Energy
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Two-Group SRE Fluxes in Two Dimensions

Technical Report ·
DOI:https://doi.org/10.2172/4238048· OSTI ID:4238048
 [1]
  1. North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.
Several two-group diffusion problems, representing the Sodium Reactor Experiment, were solved by means of NICK-2, a two-dimensional (r, z) multigroup diffusion code. The problems represented the following operational conditions: Wet criticality - 33 elements loaded and all components at a uniform temperature of 180 °C. Low temperature operation - 43 elements loaded, inlet coolant temperature 260 °C, and outlet coolant temperature 343 °C. High temperature operation - 43 elements loaded, inlet coolant temperature 260 °C, and outlet coolant temperature 516 °C. Two two-dimensional fluxes and power densities are given for the above cases. In addition, the results for reactivity and critical mass are compared with the results of the usual one-dimensional approximation, assuming separability of the fluxes in cylindrical coordinates. The close agreement obtained indicates that the one-dimensional approximation represents the two-dimensional situation quite well, even for high temperature operation.
Research Organization:
North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.
Sponsoring Organization:
US Atomic Energy Commission (AEC); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
DOE Contract Number:
AT(11-1)-GEN-8
NSA Number:
NSA-13-015777
OSTI ID:
4238048
Report Number(s):
NAA-SR--3515
Country of Publication:
United States
Language:
English