Published April 1997 | Version v1
Report Restricted

Integrity of the reactor coolant boundary of the European pressurized water reactor (EPR)

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

Restricted

The record is publicly accessible, but files are restricted to users with access.

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).

Optional Information

Secondary number(s)
CONF-9510432--.