Published 2001 | Version v1
Miscellaneous Open

Practical application of the ''compact model'' for I and C modeling in the european pressurizer reactor (EPR) probabilistic safety assessment (PSA)

  • 1. Electricite de France (EDF/DIS), Basic Design Dept., 69 - Villeurbanne (France)
  • 2. Electricite de France (EDF/DIS), Engineering and Construction Div., 92 - Montrouge (France)

Description

The EPR is an advanced Pressurized Water Reactor (PWR) under development within FRAMATOME ANP and SIEMENS NPG, and with the support of their clients: a group of major German Utilities and the French Utility (EDF). Designers have expressed their willingness to engage probabilistic studies in the design process so as to assess the safety level in order to support and to optimize the choice of design options. This practice permits to reach well-balanced design and process, and to provide a reasonable assurance that the plant design is in compliance with the general safety objectives of the EPR. A level 1 Probabilistic Safety Assessment (PSA) has been set-up. The only topic of the level 1 PSA is the core damage assessment when the fuel elements are in place in the reactor vessel. Allowance is made for internal events only, including loss of off-site power or water supplies. The all plant conditions are considered from power states to reactor coolant system open to shutdown conditions. The EPR PSA is modeled with a computer tool which enables Boolean reduction and so takes into account all dependencies between systems as common pipes, power supplies, cooling and I and C. (author)

Availability note (English)

Available from INIS in electronic form

Files

33007992.pdf

Files (137.1 kB)

Name Size Download all
md5:0074fd4c9587cab8357c380a6db1708c
137.1 kB Preview Download

Additional details

Publishing Information

Imprint Pagination
[9 p.]
Report number
INIS-FR--630

Conference

Title
9. international conference on nuclear engineering
Dates
8-12 Apr 2001
Place
Nice, Acropolis (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
33007992
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR SAFETY; REACTOR TECHNOLOGY; SIMULATION
Descriptors DEC
ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs.