Published January 1993
| Version v1
Report
Open
Thermal-hydraulic characteristics of safety systems of advanced reactors
Creators
- 1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Description
The heat transfer rates that occur inside and outside surfaces of the passive containment cooling system with both dry and wet outer containment surface following a postulated accident were investigated. The test model represented a 60 section of a containment vessel based on the AP600 geometry. The natural convective heat transfer from the containment to the air without water film flow was exceeded the expected values. Water film flow for the containment cooling is very effective to maintain the integrity of the structure of containment during postulated accident the local heat removal rate at the top of the dome is significantly higher than the average removal rate. (Author)
Availability note (English)
MF available from INIS under the Report Number.Files
24057237.pdf
Files
(3.7 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:c80c60d42bfe131b457b64e39415dfc6
|
3.7 MB | Preview Download |
Additional details
Additional titles
- Subtitle (English)
- An investigation on heat transfer in passive containment cooling system
Publishing Information
- Imprint Pagination
- 139 p.
- Report number
- KAERI/RR--1172/92
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 24057237
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Descriptors DEI
- ENGINEERED SAFETY SYSTEMS; HEAT TRANSFER; HYDRAULICS; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REYNOLDS NUMBER; TEMPERATURE DISTRIBUTION; THERMODYNAMICS
- Descriptors DEC
- COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS