Actions for Integrity of the reactor coolant boundary of the European pressurized water reactor (EPR) [electronic resource].

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Integrity of the reactor coolant boundary of the European pressurized water reactor (EPR) [electronic resource].

Published
Washington, D.C. : U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, 1997.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
pages 17-29 : digital, PDF file
Additional Creators
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
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.
Report Numbers
E 1.99:nureg/cp--0155
E 1.99: conf-9510432--
conf-9510432--
nureg/cp--0155
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
04/01/1997.
"nureg/cp--0155"
" conf-9510432--"
"TI97004806"
Seminar on leak before break in reactor piping and vessels, Lyon (France), 9-11 Oct 1995.
Schulz, H.; Jalouneix, J.; Bieniussa, K.; Goetsch, D.
View MARC record | catkey: 14363959