The effect of dissolved gas bubble nucleation on natural convection heat transfer in narrow channels

Journal Article · Tue Feb 01 00:00:00 EST 1994 · Nuclear Technology; (United States)

OSTI ID:5063649

Chao, Weiwu; Kunze, J F; Dai, Weimin; Loyalka, S K ^[1]

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1. Univ. of Missouri, Columbia, MO (United States). Nuclear Engineering Program

Research reactors present a different set of operating conditions than do light water (power) reactors (LWRs). Thermal-hydraulic transient/safety codes, such as the Reactor Loss of Coolant Analyses Program (RELAP), have been verified against experimental data from several test facilities designed for the operating conditions of LWRs. However, the operating pressures, temperatures, fuel type, and flow direction are quite different in most high-power research reactors. Furthermore, the coolant (water) in these reactors generally is not degasified and hence contains dissolved air. Results are given of benchmark experiments compared with RELAP predictions for the conditions encountered during a loss-of-coolant accident for a typical research reactor.

• OSTI ID: 5063649
• Journal Information: Nuclear Technology; (United States), Vol. 105:2; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
HEAT TRANSFER
RESEARCH REACTORS
BENCHMARKS
R CODES
REACTOR OPERATION
REACTOR SAFETY
WATER COOLED REACTORS
ACCIDENTS
COMPUTER CODES
ENERGY TRANSFER
OPERATION
REACTOR ACCIDENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors