Published 1998 | Version v1
Book Metadata-only

Corrosion-erosion, 10 years of feedback experience at EDF and optimization of the maintenance with BRT-Cicero code

Creators

  • 1. Electricite de France, 92 - Clamart (France). Service Etudes et Projets Thermiques et Nucleaires
  • 2. Electricite de France (EDF/GDL), 93 - Saint-Denis (France). Groupe des Labs
  • 3. Electricite de France (EDF) (France). CNEPE, Centre National d'Equipement de Production d'Electricite
  • 4. Electricite de France, (France). EPN, Exploitation du Parc Nucleaire

Description

The BRT-CICERO code was developed by EDF to control the damages caused by the Flow Accelerated Corrosion process in the secondary piping system. This software has now been used for 2 years in french power plants. The associated data base was build so as to ensure the exhaustibility of the risk analysis related to the FAC occurrence. BRT-CICERO was validated by using the inspection data from plants. Several actions has been carried out to reduce the code conservatisms for thickness loss evaluations. These actions were mainly related to: the revision of the geometry factors used in BRT-CICERO, the improvement of the plant data base to take into account the effect of the chromium. Moreover, the recent events of the plant experience feedback in that field were discussed and examined by using BRT-CICERO. (authors)

Part of:
Fontevraud 4. Contribution of materials investigation to the resolution of problems encountered in pressurized water reactors

Additional details

Additional titles

Original title (French)
Analyse de 10 annees de retour d'experience ''corrosion-erosion'' a Electricite de France et optimisation de la maintenance par BRT-Cicero

Publishing Information

Publisher
Societe Francaise d'Energie Nucleaire - SFEN
Imprint Place
Paris (France)
Imprint Title
Fontevraud 4. Contribution of materials investigation to the resolution of problems encountered in pressurized water reactors
Imprint Pagination
(v.2) 581 p.
Journal Page Range
p. 1001-1011

Conference

Title
International symposium Fontevraud 4. Contribution of materials investigation to the resolution of problems encountered in pressurized water reactors
Dates
14-18 Sep 1998
Place
Paris (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
31012138
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
B CODES; CARBON STEELS; CHROMIUM; COMPUTERIZED SIMULATION; CORROSION; EROSION; PWR TYPE REACTORS; REACTOR MAINTENANCE; SECONDARY COOLANT CIRCUITS
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; COMPUTER CODES; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; IRON ALLOYS; IRON BASE ALLOYS; MAINTENANCE; METALS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs. Imprint:Fontevraud 4. Contribution des expertises sur materiaux a la resolution des problemes rencontres dans les reacteurs a eau pressurisee