Thermal-hydraulics of a steam discharge system
Creators
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Description
Physical characteristics of the steam discharge system of PWR, which consists of valves, piping, steam sparger, and steam accommodating tank, have been analyzed and the analysis system has been set up for development of the analysis and design methodology for the system. The work was the results of the final year research in the planned research period of three years. Analysis has been made for the characteristics of rapid transient and steady flow in the piping, bubble behavior and wall pressure oscillation in a large and open tank, steam condensation, thermal mixing performance in a pool, and small and hermetically sealed tank performance. Based on the analysis results, experimental requirements for the development provided. Finally, for the further work in developing KNGR, the implementing approach related to this work has been purposed. 42 figs, 2 tabs, 29 refs. (Author)
Availability note (English)
MF available from INIS under the Report Number.Files
27015512.pdf
Files
(3.1 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 117 p.
- Report number
- KAERI-RR--1440/94
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 27015512
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BUBBLES; FLUID FLOW; HYDRAULICS; MECHANICAL VIBRATIONS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; STEAM LINES; THERMODYNAMICS; VAPOR CONDENSATION
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; PIPELINES; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS