Mitigation of flooding under externally imposed oscillatory gas flow
Creators
- 1. Cheju National Univ., Cheju (Korea, Republic of)
- 2. McMaster University, Hamilton (United States)
Description
During the hypothetical loss of coolant accident in the nuclear power plant, the emergency core cooling water could not penetrate to the reactor core when the steam flow rate from the reactor core exceeds CCFL (Countercurrent Flow Iimitation). The CCFL generated by earlier investigators are developed under the steady gas flow. However the flow instability in the reactor loop could generate oscillatory steam flow, hence their applicability under oscillating flow should be investigated. In this work, an experimental investigation of countercurrent flow in the vertical flow channel has been conducted under oscillatory gas flow. Pulsation of gas under oscillatory flow disturbs the flow pattern significantly and prevents flooding (CCFL) when its minimum value is less than the threshold gas flow rate value
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- 1059 p.
- Journal Page Range
- p. 475-479
Conference
- Title
- 1995 autumn meeting of the KNS
- Dates
- 28 Oct 1995
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 37117413
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FLOW RATE; GAS FLOW; LOSS OF COOLANT; NUCLEAR POWER PLANTS; OSCILLATORS; REACTOR CORES
- Descriptors DEC
- ACCIDENTS; ELECTRONIC EQUIPMENT; EQUIPMENT; FLUID FLOW; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; THERMAL POWER PLANTS
Optional Information
- Notes
- 4 refs, 4 figs