Natural circulation cooling for lead-bismuth cooled simple reactor
Creators
- 1. Department of Nuclear Engineering, Oregon State University, Corvallis, Oregon 97331 (United States)
Description
This study investigates the maximum power output that can be removed using natural circulation alone in a small, 150-MWt reactor cooled with lead-bismuth mixture. First, a simple natural circulation model in the core will be analyzed. Then the model will be coupled with the secondary extemal cooling system to make it more realistic. Two possible directions of forced secondary flow were analyzed: a concurrent flow with the primary reactor coolant flow, and a countercurrent flow that would flow against the primary coolant flow. Flow equations were derived from the conservation of momentum equation, which was simplified to the differential pressure loss through the core and the driving differential pressure due to buoyancy forces. A parametric study was conducted on the effect of varying reactor height, secondary coolant velocity, fuel pitch, and fuel height, in order to determine the maximum amount of heat that can be removed from the core. The results show that it is not feasible to cool 150-MW of heat using natural circulation, however the decay heat may be removed for a vessel that is 20 m high
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- Jackson Hole, Wyoming (United States)
- Imprint Pagination
- 3 p.
Conference
- Title
- International Conference on Future Nuclear Systems - Nuclear Technology - Bridging the Millennia
- Acronym
- Global'99
- Dates
- 29 Aug - 3 Sep 1999
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 53059541
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; BUOYANCY; COOLANTS; COOLING; NATURAL CONVECTION; NUCLEAR FUELS; PARAMETRIC ANALYSIS; PRIMARY COOLANT CIRCUITS
- Descriptors DEC
- CONVECTION; COOLING SYSTEMS; ENERGY SOURCES; ENERGY SYSTEMS; ENERGY TRANSFER; FUELS; HEAT TRANSFER; MASS TRANSFER; MATERIALS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR MATERIALS
Optional Information
- Notes
- 6 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)