Analysis of External Cooling of the Reactor Vessel During Severe Accidents
Creators
- 1. Korea Atomic Energy Research Institute (Korea, Republic of)
Description
An analysis is presented of the integral behavior of the external cooling of a reactor vessel by natural circulation during a severe accident to investigate the feasibility of the in-vessel retention strategy for a high-power reactor by using the RELAP5/MOD3 computer code. It is shown that two-phase flow instability phenomena, including natural-circulation oscillation and density wave oscillations, affect the local thermal margin at the reactor vessel wall. The heat load on the reactor vessel is simplified as a uniform heat flux load of 600 kW/m2 in the base case. A sensitivity study for the effect of the inlet K factor, nonuniform heat flux distribution, inlet flow area, and subcooling of the pool water is performed to evaluate the local thermal margin. The results of the analysis show that natural-circulation cooling is marginal at this level of heat flux. It also clearly indicates that a system level of analysis for two-phase natural circulation, including the sensitivity study on the design parameters, is necessary to ensure successful implementation of the external cooling
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 138
- Journal Issue
- 1
- Journal Page Range
- p. 79-89
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 38002177
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ACCIDENTS; DENSITY; DESIGN; HEAT FLUX; HEATING LOAD; INSTABILITY; NATURAL CONVECTION; POWER REACTORS; R CODES; REACTOR VESSELS; SENSITIVITY ANALYSIS; SUBCOOLING; TWO-PHASE FLOW; WATER
- Descriptors DEC
- COMPUTER CODES; CONTAINERS; CONVECTION; COOLING; ENERGY TRANSFER; FLUID FLOW; HEAT TRANSFER; HYDROGEN COMPOUNDS; MASS TRANSFER; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; REACTORS
Optional Information
- Copyright
- Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/