Published 1993
| Version v1
Journal article
Integral testing of the AP600 passive emergency core cooling systems
- 1. Westinghouse Electric Corp., Pittsburgh, PA (United States)
Description
Its support of the development of AP600, Westinghouse is conducting two integral systems tests to examine the performance of the passive safety systems. A full-height, full pressure test is being performed to simulate a small loss-of-coolant, steam generator tube rupture and large steam line break events. A one-quarter scale, low pressure test is being performed to simulate transients with emphasis on the transition to the natural circulation post-accident, long-term cooling mode and to demonstrate the long-term cooling capability. Each of the tests will provide detailed experimental results for verification of the accident analysis computer codes. (Author)
Additional details
Publishing Information
- Journal Title
- Proceedings of the Institution of Mechanical Engineers. Part A, Journal of Power and Energy
- Journal Volume
- 207
- Journal Issue
- A4
- Journal Page Range
- p. 259-268.
- ISSN
- 0957-6509
- CODEN
- PMAEET
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 25049998
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ECCS; LOSS OF COOLANT; NATURAL CONVECTION; PERFORMANCE TESTING; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RUPTURES; SCALE MODELS; SPECIFICATIONS; STEAM GENERATORS; STEAM LINES
- Descriptors DEC
- ACCIDENTS; BOILERS; CONVECTION; COOLING SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; HEAT TRANSFER; PIPELINES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; STRUCTURAL MODELS; TESTING; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS