Published 1993
| Version v1
Book
Integral testing of the AP600 passive emergency core cooling systems
- 1. Westinghouse Electric Corp., Pittsburgh, PA (United States)
Description
In support of the development of the AP600, Westinghouse is conducting two integral system tests to examine the performance of the passive safety systems. A full-height, full-pressure test is being performed to simulate 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 convection 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
- Publisher
- Mechanical Engineering Publications Ltd.
- Imprint Place
- London (United Kingdom)
- ISBN
- 0 85298 860 5
- Imprint Title
- Nuclear power plant safety standards: towards international harmonization
- Imprint Pagination
- 320 p.
- Journal Issue
- no. 1993-8
- Series
- Proceedings of the Institution of Mechanical Engineers (IMechE).
- Journal Page Range
- p. 101-114.
Conference
- Title
- towards international harmonization.
- Acronym
- International conference on nuclear power plant safety standards
- Dates
- 26-28 Oct 1993.
- Place
- London (United Kingdom).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 25044795
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; ECCS; LOSS OF COOLANT; NATURAL CONVECTION; PERFORMANCE TESTING; PWR TYPE REACTORS; REACTOR SAFETY; RUPTURES; SCALE MODELS; STEAM GENERATORS; STEAM LINES; TRANSIENTS; USA
- Descriptors DEC
- ACCIDENTS; BOILERS; CONVECTION; DEVELOPED COUNTRIES; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; HEAT TRANSFER; NORTH AMERICA; PIPELINES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SIMULATION; STRUCTURAL MODELS; TESTING; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS