Published 1995 | Version v1
Miscellaneous

Mitigation of flooding under externally imposed oscillatory gas flow

  • 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

Part of:
Proceedings of the KNS autumn meeting

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