The Effects of Swirl Flow on CHF by Various Spacer Grids in 2*2 Rod Bundle with R-134a
- Korea Advanced Institute of Science and Technology, 373-1, Guseong-dong, Yuseong-gu, Daejeon, 305-701 (Korea, Republic of)
Experimental works have shown that the effect of swirl flow on CHF by various spacer grid in the 2*2 rod bundle with R-134a. Test spacer grids have mixing vanes for generating swirl flow. The geometries of test section are as follows; rod diameter is 9.5 mm, rod pitch is 12.85 mm. For test spacer grid, two different types are used changing the angle of mixing vanes. In CHF test, experimental conditions are as follows; mass flux is from 1000 to 1800 kg/m{sup 2}s, inlet subcooling from 40.21 kJ/kg to 129.5 kJ/kg, and inlet pressure is from 15 bar to 25 bar. The locations of spacer grid are 200 mm upstream from the end of heating rod. Pressure drop was also measured in single phase experiment. Consequently, the magnitude of swirl flow is related to CHF. Namely, as swirl flow is stronger, the CHF enhance more. The type and angle of mixing vane are effective to swirl flow. And, because swirl flow decays along the flow stream, CHF enhancement decreases along the flow direction. Therefore, in nuclear fuel development, it is important to consider flow structure in a subchannel because CHF enhancement is up to 21% according to circumstances. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 21160662
- Resource Relation:
- Conference: ICAPP'04: 2004 international congress on advances in nuclear power plants, Pittsburgh, PA (United States), 13-17 Jun 2004; Other Information: Country of input: France; 17 refs; Related Information: In: Proceedings of the 2004 international congress on advances in nuclear power plants - ICAPP'04, 2338 pages.
- Country of Publication:
- United States
- Language:
- English
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