Integrity of the reactor coolant boundary of the European pressurized water reactor (EPR)
Creators
Description
This paper is an abstract of the work performed in the frame of the development of the IPSN/GRS approach in view of the EPR conceptual safety features. EPR is a pressurized water reactor which will be based on the experience gained by utilities and designers in France and in Germany. The reactor coolant boundary of a PWR includes the reactor pressure vessel (RPV), those parts of the steam generators (SGs) which contain primary coolant, the pressurizer (PSR), the reactor coolant pumps (RCPs), the main coolant lines (MCLs) with their branches as well as the other connecting pipes and all branching pipes including the second isolation valves. The present work covering the integrity of the reactor coolant boundary is mainly restricted to the integrity of the main coolant lines (MCLs) and reflects the design requirements for the main components of the reactor coolant boundary. In the following the conceptual aspects, i.e. design, manufacture, construction and operation, will be assessed. A main aspect is the definition of break postulates regarding overall safety implications
Files
Additional details
Publishing Information
- Imprint Title
- Proceedings of the seminar on leak before break in reactor piping and vessels
- Imprint Pagination
- 773 p.
- Journal Page Range
- p. 17-29.
- Report number
- NUREG/CP--0155
Conference
- Title
- Seminar on leak before break in reactor piping and vessels.
- Dates
- 9-11 Oct 1995.
- Place
- Lyon (France).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28076012
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FRENCH ORGANIZATIONS; GESELLSCHAFT FUER ANLAGEN- UND REAKTORSICHERHEIT; LEAKS; PIPES; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; SAFETY ANALYSIS
- Descriptors DEC
- COOLING SYSTEMS; ENRICHED URANIUM REACTORS; GERMAN FR ORGANIZATIONS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-9510432--.