TERMIUM Plus®

The Government of Canada’s terminology and linguistic data bank.

CIRCUIT REFROIDISSEMENT INTERMEDIAIRE [1 record]

Filter results by subject field Alphabetical list of terms

Filter results by subject field

Alphabetical list of terms

Record 1 2015-04-28

English

Subject field(s)
  • Nuclear Fission Reactors
DEF

A sodium coolant circuit in a sodium-cooled fast reactor that transfers heat from the radioactive primary coolant circuit to the circuit containing the working medium, for example water; it prevents contact between the radioactive coolant and water.

OBS

intermediate coolant circuit: term and definition standardized by ISO.

French

Domaine(s)
  • Réacteurs nucléaires de fission
DEF

Circuit de sodium dans un réacteur rapide refroidi au sodium, transférant la chaleur du circuit primaire radioactif de refroidissement au circuit contenant le milieu de travail, par exemple de l'eau; il prévient tout contact entre le fluide de refroidissement radioactif et l'eau.

OBS

circuit de refroidissement intermédiaire : terme et définition normalisés par l'ISO.

Spanish

Save record 1

Copyright notice for the TERMIUM Plus® data bank

© Public Services and Procurement Canada, 2024
TERMIUM Plus®, the Government of Canada's terminology and linguistic data bank
A product of the Translation Bureau

Display options

Change the order of display of the official languages of Canada
Option to display the non-official languages (Spanish or Portuguese)
Display definitions, contexts, etc., on records

Features

Language Portal of Canada

Access a collection of Canadian resources on all aspects of English and French, including quizzes.

Writing tools

The Language Portal’s writing tools have a new look! Easy to consult, they give you access to a wealth of information that will help you write better in English and French.

Glossaries and vocabularies

Access Translation Bureau glossaries and vocabularies.

Date Modified: