Published 1991 | Version v1
Journal article

An attempt for qualification in nuclear industry: the specific instance of the qualification of valves under accidental conditions of operation

Creators

  • 1. Electricite de France (EDF), 69 - Lyon (France). Region d'Equipement

Description

A nuclear French plant of the pressurized water type requires about 12,000 valves in order to monitor the internal flow of fluids (essentially water and vapor). The pressure range can reach and even exceed 150 bar, with diameters ranging between 8 mm and 1 m, and eventually more than that. This wide variety of conditions unveils two major questions for the designer and user to worry with: - to hold the reactor in a state that will not entail unacceptable consequences for the inhabitants in any kind of event, - to avoid as much as possible non intentional shutdowns, which are quite costly for an industrial plant of that size. In order to comply with these two problems, and particularly for the fitting of valves, a high reliability is required for running the equipment. This reliability follows from a global procedure with regard to the main objective at every step: - design: importance of the technical specifications and of the coding process used (RCCM); - manufacture: monitoring plays an essential part at this stage; - starting procedures of the equipment (without or with fluid circulation); - maintenance and recurrent testing procedures; - sampling and accounting for feed back informations and to be sure, laboratory testing for qualification, which should encompass the whole field of operation including even the so-called accidental conditions. This last point is dealt with in the following paper

Abstract (French)

Une centrale nucleaire francaise de la filiere a eau pressurisee necessite environ 12 000 robinets pour assurer le controle des fluides (essentiellement eau et vapeur) qui y circulent. La gamme de pression atteint et depasse parfois les 150 bar tandis que les diametres s'etagent entre 8 mm et 1 m, voire au-dela. Toutefois, cette diversite laisse emerger deux preoccupations majeures pour le concepteur et l'exploitant: - maintenir, en toutes circonstances, le reacteur dans un etat n'engendrant pas de consequences inacceptables pour la population; - limiter au maximum les arrets non programmes, tres couteux, pour une installation industrielle de cette taille. Ces deux objectifs requierent des fonctions et materiels utilises et donc, en particulier, de la robinetterie, une tres grande fiabilite. Cette fiabilite elle-meme resulte d'une approche globale integrant a tous les stades elementaires l'objectif initial: - conception: importance de la definition du cahier des charges et des codes utilises (Regles de Conception et de Construction des Materiels Mecaniques - RCCM); - fabrication: il faut noter ici la contribution fondamentale des controles; - essais au demarrage de l'installation (hors et avec fluide); - maintenance et essais periodiques; - collecte et integration du retour d'experience, et, bien sur, essais de qualification en laboratoire, lesquels doivent couvrir le domaine de fonctionnement normal mais egalement les conditions dites accidentelles. Ce qui suit developpe ce dernier aspect

Additional details

Additional titles

Original title (French)
Essais de qualification dans l'industrie nucleaire: le cas particulier de la qualification de la robinetterie aux conditions accidentelles de fonctionnement

Publishing Information

Journal Title
RFM. Revue Francais de Mecanique
Journal Issue
no.3
Series
RFM, Rev. Fr. Mec.
ISSN
0373-6601
CODEN
RFMQA

Conference

Title
Test standardization in mechanics, the european deadline.
Original Conference Title
Journees S.F.M./F.I.M.T.M.: Normalisation des essais en mecanique l'echeance europeenne
Acronym
S.F.M./F.I.M.T.M. seminar
Dates
22 Nov 1990.
Place
Paris (France).

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
23067906
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
MECHANICAL TESTS; PIPE WHIP; PWR TYPE REACTORS; QUALITY ASSURANCE; SEISMIC EFFECTS; VALVES
Descriptors DEC
CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; MATERIALS TESTING; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS