Published 1983 | Version v1
Book

Study of the formation and transport of corrosion products in PWR primary circuit simulators

  • 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Dept. des Reacteurs a Eau
  • 2. Centre d'Etudes et de Recherches, Electricite de France, Les Renardieres

Description

The formation, migration and deposition of corrosion products in PWR primary circuits are studied in out-of-reactor loops. The aim of these studies is to limit the build-up of the radiation fields impinging on out-of-flux walls and to reduce the danger of rapid corrosion of fuel cans, taking into account the tougher conditions imposed on current trends in the operation of such industrial plants. Four simulator loops and their respective possibilities and research methods are described. (author)

Additional details

Additional titles

Original title (French)
Etude de la formation et du transport des produits de corrosion dans des installations de simulation de circuits primaires de reacteurs a eau sous pression

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna
ISBN
92-0-050783-2
Imprint Title
Water chemistry and corrosion problems in nuclear power plants
Imprint Pagination
517 p.
Series
Proceedings series.
Journal Page Range
p. 379-400.

Conference

Title
International symposium on water chemistry and corrosion problems of nuclear reactor systems and components.
Dates
22-26 Nov 1982.
Place
Vienna (Austria).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
15003121
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CORROSION; CORROSION PRODUCTS; FUEL CANS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR SIMULATORS; SPECIFICATIONS
Descriptors DEC
ANALOG SYSTEMS; CHEMICAL REACTIONS; COOLING SYSTEMS; FUNCTIONAL MODELS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
IAEA-SM--264/20.