TERMIUM Plus®
The Government of Canada’s terminology and linguistic data bank.
CALOPORTEUR REACTEUR [4 records]
Record 1 - internal organization data 2024-06-11
Record 1, English
Record 1, Subject field(s)
- Nuclear Fission Reactors
- Nuclear Power Stations
Record 1, Main entry term, English
- sodium-cooled fast reactor
1, record 1, English, sodium%2Dcooled%20fast%20reactor
correct
Record 1, Abbreviations, English
- SFR 2, record 1, English, SFR
correct
Record 1, Synonyms, English
- sodium-cooled fast neutron reactor 3, record 1, English, sodium%2Dcooled%20fast%20neutron%20reactor
correct
Record 1, Textual support, English
Record number: 1, Textual support number: 1 DEF
A fast neutron reactor using liquid sodium as coolant. 4, record 1, English, - sodium%2Dcooled%20fast%20reactor
Record 1, Key term(s)
- sodium cooled fast reactor
- sodium cooled fast neutron reactor
Record 1, French
Record 1, Domaine(s)
- Réacteurs nucléaires de fission
- Centrales nucléaires
Record 1, Main entry term, French
- réacteur rapide refroidi au sodium
1, record 1, French, r%C3%A9acteur%20rapide%20refroidi%20au%20sodium
correct, masculine noun
Record 1, Abbreviations, French
- RNR-Na 2, record 1, French, RNR%2DNa
correct, masculine noun
Record 1, Synonyms, French
- réacteur à neutrons rapides refroidi au sodium 3, record 1, French, r%C3%A9acteur%20%C3%A0%20neutrons%20rapides%20refroidi%20au%20sodium
correct, masculine noun
- réacteur rapide à caloporteur sodium 4, record 1, French, r%C3%A9acteur%20rapide%20%C3%A0%20caloporteur%20sodium
correct, masculine noun
Record 1, Textual support, French
Record number: 1, Textual support number: 1 DEF
Réacteur à neutrons rapides dont le caloporteur est du sodium liquide. 1, record 1, French, - r%C3%A9acteur%20rapide%20refroidi%20au%20sodium
Record number: 1, Textual support number: 1 OBS
réacteur rapide refroidi au sodium; RNR-Na : terme, abréviation et définition publiés au Journal officiel de la République française le 16 juin 2004. 5, record 1, French, - r%C3%A9acteur%20rapide%20refroidi%20au%20sodium
Record 1, Spanish
Record 1, Textual support, Spanish
Record 2 - internal organization data 2021-07-14
Record 2, English
Record 2, Subject field(s)
- Cooling and Ventilating Systems
- Nuclear Fission Reactors
Record 2, Main entry term, English
- reactor coolant
1, record 2, English, reactor%20coolant
correct
Record 2, Abbreviations, English
Record 2, Synonyms, English
Record 2, French
Record 2, Domaine(s)
- Systèmes de refroidissement et de ventilation
- Réacteurs nucléaires de fission
Record 2, Main entry term, French
- caloporteur de réacteur
1, record 2, French, caloporteur%20de%20r%C3%A9acteur
masculine noun
Record 2, Abbreviations, French
Record 2, Synonyms, French
Record 2, Textual support, French
Record 2, Spanish
Record 2, Textual support, Spanish
Record 3 - external organization data 2000-08-09
Record 3, English
Record 3, Subject field(s)
- Nuclear Fission Reactors
- Compartment - Canadian Nuclear Safety Commission
Record 3, Main entry term, English
- reactor coolant main circulating pump
1, record 3, English, reactor%20coolant%20main%20circulating%20pump
correct
Record 3, Abbreviations, English
Record 3, Synonyms, English
Record 3, French
Record 3, Domaine(s)
- Réacteurs nucléaires de fission
- Tiroir - Commission canadienne de sûreté nucléaire
Record 3, Main entry term, French
- pompe du système caloporteur primaire du réacteur
1, record 3, French, pompe%20du%20syst%C3%A8me%20caloporteur%20primaire%20du%20r%C3%A9acteur
feminine noun
Record 3, Abbreviations, French
Record 3, Synonyms, French
Record 3, Textual support, French
Record 3, Spanish
Record 3, Textual support, Spanish
Record 4 - internal organization data 1993-08-31
Record 4, English
Record 4, Subject field(s)
- Titles of Documents and Works
Record 4, Main entry term, English
- Post-test simulation of BTF-107: an in-reactor loss of coolant test with flow blockage and rewet
1, record 4, English, Post%2Dtest%20simulation%20of%20BTF%2D107%3A%20an%20in%2Dreactor%20loss%20of%20coolant%20test%20with%20flow%20blockage%20and%20rewet
correct, Canada
Record 4, Abbreviations, English
Record 4, Synonyms, English
- Post-test simulation of BTF-107 1, record 4, English, Post%2Dtest%20simulation%20of%20BTF%2D107
correct, Canada
Record 4, Textual support, English
Record number: 4, Textual support number: 1 OBS
Atomic Energy of Canada Limited publication AECL 10758, 1992. 2, record 4, English, - Post%2Dtest%20simulation%20of%20BTF%2D107%3A%20an%20in%2Dreactor%20loss%20of%20coolant%20test%20with%20flow%20blockage%20and%20rewet
Record 4, French
Record 4, Domaine(s)
- Titres de documents et d'œuvres
Record 4, Main entry term, French
- Simulation après essai de la BFT-107(IED-107) : essai de perte de caloporteur en réacteur avec obstruction des canaux de circulation et remouillage
1, record 4, French, Simulation%20apr%C3%A8s%20essai%20de%20la%20BFT%2D107%28IED%2D107%29%20%3A%20essai%20de%20perte%20de%20caloporteur%20en%20r%C3%A9acteur%20avec%20obstruction%20des%20canaux%20de%20circulation%20et%20remouillage
correct, Canada
Record 4, Abbreviations, French
Record 4, Synonyms, French
- Simulation après essai de la BFT-107 (IED-107) 1, record 4, French, Simulation%20apr%C3%A8s%20essai%20de%20la%20BFT%2D107%20%28IED%2D107%29
correct, Canada
Record 4, Textual support, French
Record number: 4, Textual support number: 1 OBS
Publication AECL 10758 d'Énergie atomique du Canada Limitée, 1992. 2, record 4, French, - Simulation%20apr%C3%A8s%20essai%20de%20la%20BFT%2D107%28IED%2D107%29%20%3A%20essai%20de%20perte%20de%20caloporteur%20en%20r%C3%A9acteur%20avec%20obstruction%20des%20canaux%20de%20circulation%20et%20remouillage
Record 4, Spanish
Record 4, Textual support, Spanish
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