Experimental and analytical investigation of a PWR natural circulation loop
- 1. Electric Power Research Inst., Palo Alto, CA
Description
A theoretical and experimental study of a natural circulation loop relevant to PWRs is presented. The analysis is based on a one-dimensional model in which the continuity momentum and energy equations are given and solved. The steady-state and transient flow rates and temperatures are derived. The apparatus consisted of an electrically-heated section and two parallel loops with heat exchangers. Both steady-state and transient experiments were conducted to study the effects of the core flow resistance, the power distribution, and the upper plenum design. Flow oscillations were observed under certain conditions, which were accompained by instabilities and flow reversals. Reasonable agreement (+-30%) is obtained between the analytical and experimental results and with available plant data
Additional details
Publishing Information
- Imprint Title
- Thermal Reactor Safety
- Journal Page Range
- p. 153-161.
- Report number
- CONF-800403--(Vol.1)
Conference
- Title
- ANS thermal reactor safety meeting.
- Dates
- 8 - 11 Apr 1980.
- Place
- Knoxville, TN, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12573522
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FLOW RATE; HEAT TRANSFER; HYDRAULICS; LOSS OF FLOW; MOCKUP; NATURAL CONVECTION; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; CONVECTION; COOLING SYSTEMS; DISTRIBUTION; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS