The analysis of reactor vessel integrity for DVI application
Creators
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Description
To investigate some licensing questions on the integrity of reactor pressure vessel due to DVI, which injects relatively cold safety injection water into the reactor vessel downcomer and aggravates pressurized thermal shock (PTS), can be raised, related activities, which are as following, have been done : * Physical phenomena of PTS review * USNRC PTS Screening Criteria review * Review of USNRC PTS Screening Criteria applicability to KNGR * Review of KNGR design features vs PTS Rule background * Emergency core cooling water mixing preliminary analysis in reactor vessel downcomer. USNRC PTS Screening Criteria has been adopted as the design criteria for KNG PTS concerning due to DVI. In the view point of performance, a preliminary mixing analysis in reactor vessel downcomer has been done to optimize the DVI nozzle position and further works to done are provided. 11 figs., 13 refs. (Author) .new
Availability note (English)
MF available from INIS under the Report Number.Files
27063030.pdf
Files
(1.1 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 37 p.
- Report number
- KAERI/TR--610/95
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 27063030
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
- Descriptors DEI
- EMBRITTLEMENT; FRACTURE PROPERTIES; HIGH PRESSURE COOLANT INJECTION; LOW PRESSURE COOLANT INJECTION; PROBABILISTIC ESTIMATION; REACTOR SAFETY; REACTOR VESSELS; THERMAL STRESSES
- Descriptors DEC
- CONTAINERS; ECCS; ENGINEERED SAFETY SYSTEMS; MECHANICAL PROPERTIES; REACTOR PROTECTION SYSTEMS; SAFETY; STRESSES