BURN-OUT ANALYSIS. PART 5. EXAMINATION OF PUBLISHED WORLD DATA FOR ROD BUNDLES
Technical Report
·
OSTI ID:4012672
Burn-out data and descriptive details of 24 different rod bundle geometries have been compiled and subjected to analysis. The majority are at about 1,000 p.s.i.a. and the conclusions reached refer mainly to this pressure with forced convection and with liquid water inlet. The most important conclusion is that details of the internal structure of a bundle in general have no effect on burn-out, and this is substantiated by a wide variety of rod supports and spacers used. The only important cross-sectional geometry parameter has been identified as the heated equivalent diameter (4 x flow area/heated perimeter). Another important conclusion is that due to gravity, the burn-out flux in horizontal rod bundles can be as much as 50% below that for similar vertical bundles with upflow. A further drop in burn-out flux may also occur in horiziontal channels due to severe flow stratification. A local conditions type of burn-out equation is presented which predicts 97% of the 1,000 p.s.i.a. data within +- 12%. The equation has been used to examine the optimisation of rod diameter and number of rods in a bundle to give maximum power output. (auth)
- Research Organization:
- United Kingdom Atomic Energy Authority. Reactor Group. Atomic Energy Establishment, Winfrith, Dorset, England (United Kingdom)
- NSA Number:
- NSA-18-041611
- OSTI ID:
- 4012672
- Report Number(s):
- AEEW-R-358
- Country of Publication:
- United Kingdom
- Language:
- English
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