Safety analysis calculations for a mixed and full FLIP core in a TRIGA Mark II
Conference
·
OSTI ID:21152779
- Oregon State University, Corvallis, OR (United States)
The Oregon State TRIGA Reactor will be reloading with FLIP fuel in August 1976. As we are the first Mark II TRIGA with a circular grid pattern and graphite reflector to utilize FLIP fuel, the safety analysis calculations performed at other facilities using FLIP were only of limited use to us. A multigroup, multiregion, one-dimensional diffusion theory code was used to calculate power densities in six different operational cores - mixed to full FLIP. Pulsing characteristics were obtained from a computer code based on point kinetics, with adiabatic heating of the fuel, linear temperature dependence of the specific heat, and prompt fuel temperature feedback coefficient. The results of all pertinent calculations will be presented. (author)
- Research Organization:
- General Atomic Co., San Diego, CA (United States); University of California, Berkeley, CA (United States)
- OSTI ID:
- 21152779
- Report Number(s):
- INIS-US--09N0184; TOC--7
- Country of Publication:
- United States
- Language:
- English
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