Published 1980 | Version v1
Book Metadata-only

Study of friction and wear conditions of control rod drive and control cluster in PWR

Creators

  • 1. Societe Franco-Americaine de Constructions Atomiques (FRAMATOME), 92 - Courbevoie (France)

Description

A good wear resistance is needed for control rod drive, control cluster and fixed guiding systems in internal structure of reactor primary circuit. In an experimental programme life-size material is verified with pressurized water in a loop called SUPERBEC at Cadarache and a research programme is set to find pairs of materials to reduce wear of fixed and moving parts. This programme is divided in three phases: first examination of control rod drive and guide wear, then reproducing wear in a laboratory test and study of material pairs and finally testing of materials in the pressurized water loop

Abstract (French)

Les mecanismes de commande, les grappes de controle, les organes fixes du guidage dans les structures internes du reacteur doivent presenter une bonne resistance a l'usure en milieu primaire. Pour le verifier on a engage un programme d'experimentation en vraie grandeur du materiel en milieu eau pressurisee sur la boucle SUPERBEC a Cadarache, et un programme de recherche de couples de materiaux en vue de reduire l'usure des organes fixes et mobiles. Les differentes phases de ce programme sont les suivantes: examen des zones d'usure des mecanismes de commande des grappes et des guides de grappes. Simulation de cette usure sur des machines de frottement de laboratoire et essais de couples de materiaux. Experimentation des solutions les plus interessantes en milieu eau pressurisee
Part of:
International colloquium on hard-facing materials in nuclear power plants

Additional details

Additional titles

Original title (French)
Etude des conditions de frottement et d'usure des mecanismes de commande et des grappes de controle dans les reacteurs a eau sous pression

Publishing Information

Publisher
SFEN.
Imprint Place
Paris, France
Imprint Title
International colloquium on hard-facing materials in nuclear power plants, Avignon, 25-26 September 1980
Imprint Pagination
235 p.
Journal Page Range
p. 167-178.

Conference

Title
International colloquium on hard-facing materials in nuclear power plants.
Dates
25 - 26 Sep 1980.
Place
Avignon, France.

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
12599076
Subject category
S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CHROMIUM; COLMONOY; CONTROL ROD DRIVES; FRICTION; PWR TYPE REACTORS; STELLITE; STELLITE 6; WEAR; WEAR RESISTANCE
Descriptors DEC
ALLOYS; CHROMIUM ALLOYS; COBALT ALLOYS; COBALT BASE ALLOYS; ELEMENTS; HEAT RESISTING ALLOYS; IRON ALLOYS; MECHANICAL PROPERTIES; METALS; NICKEL ALLOYS; NICKEL BASE ALLOYS; REACTOR COMPONENTS; REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; TUNGSTEN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:Colloque international sur les materiaux durs pour frottement dans les reacteurs nucleaires, Avignon, 25-26 septembre 1980.