An evaluation of thermal-hydrodynamics for condensation pool and piping system
Creators
- 1. Kyungpook National Univ., Daegu (Korea, Republic of)
Description
If the steam with high pressure and high temperature at APR-1400 is discharged into IRWST through, the spargers submerged into it to release the pressure of coolant system 10 accident. The shock wave accompanying unsteady flow motion is propagated through the various piping system, it exerts high pressure load on units and may cause the structural problems and severe vibration. From the viewpoint of nuclear power plant safety, The analysis of flow behaviors 10 the IRWST and piping system is essential to achieve the technology for the evaluation of safety. And also he evaluation methods by the analysis of thermal hydrodynamic behaviors through the sparger is established. The results obtained show that the initial shock wave experienced reflection, diffraction and interaction with shock-induced vortex. The time-dependent maximum load exerted on the wall is largest 10 the T-junction, while the smallest 10 the branch. It is found that because there is nearly no change 10 pressure at condensation pool during water clearing, the system appears to be safe. However, calculations of the air clearing for 0.2 second were performed using VOF model to analyze air that coexist with water between load reduction and sparger head. In addition, since actual POSRV opening takes finite time of 1.7 second, it is expected that the flow field will be different from the that of instant opening the valve. Therefore, now the grid generation is proceeded for the case of POSRV opening at finite time of 1.7 second consecutively. The future study alms at flow analysis of POSRV opening at finite time, changing boundary conditions for wall into pressure inlet
Availability note (English)
Available from INIS in electronic form; Also available from KINSFiles
37122427.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 47 p.
- Report number
- KINS/HR--520
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 37122427
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- EVALUATION; PIPES; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; SHOCK TUBES; SPARGERS; THERMAL HYDRAULICS
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 13 refs, 25 figs