TERMIUM Plus®
The Government of Canada’s terminology and linguistic data bank.
LOCA [15 records]
Record 1 - internal organization data 2016-11-30
Record 1, English
Record 1, Subject field(s)
- Nuclear Fission Reactors
Record 1, Main entry term, English
- advanced boiling water reactor
1, record 1, English, advanced%20boiling%20water%20reactor
correct
Record 1, Abbreviations, English
- ABWR 1, record 1, English, ABWR
correct
Record 1, Synonyms, English
Record 1, Textual support, English
Record number: 1, Textual support number: 1 CONT
The Advanced Boiling Water Reactor(ABWR) is an improved design of [a] boiling water reactor. The ABWR was designed by General Electric as their generation III reactor. One chief improvement is that the recirculation pumps and piping are contained inside the reactor pressure vessel, thus making it impossible for them to leak outside of the vessel. Also, in the event of a loss of coolant accident(LOCA), plant response has been fully automated and operator action is not required for 3 days. These and other improvements make the plant significantly safer than previous reactors. 2, record 1, English, - advanced%20boiling%20water%20reactor
Record number: 1, Textual support number: 1 OBS
advanced boiling water reactor; ABWR: term and abbreviation extracted from the “Glossaire de l’énergie nucléaire” and reproduced with permission of the Organisation for Economic Co-operation and Development. 3, record 1, English, - advanced%20boiling%20water%20reactor
Record 1, French
Record 1, Domaine(s)
- Réacteurs nucléaires de fission
Record 1, Main entry term, French
- réacteur à eau bouillante de type avancé
1, record 1, French, r%C3%A9acteur%20%C3%A0%20eau%20bouillante%20de%20type%20avanc%C3%A9
masculine noun
Record 1, Abbreviations, French
Record 1, Synonyms, French
- REB de type avancé 1, record 1, French, REB%20de%20type%20avanc%C3%A9
masculine noun
- réacteur à eau bouillante avancé 2, record 1, French, r%C3%A9acteur%20%C3%A0%20eau%20bouillante%20avanc%C3%A9
masculine noun
Record 1, Textual support, French
Record number: 1, Textual support number: 1 OBS
réacteur à eau bouillante de type avancé; REB de type avancé : termes extraits du «Glossaire de l’énergie nucléaire» et reproduits avec l’autorisation de l’Organisation de coopération et de développement économiques. 3, record 1, French, - r%C3%A9acteur%20%C3%A0%20eau%20bouillante%20de%20type%20avanc%C3%A9
Record 1, Key term(s)
- réacteur de type avancé à eau bouillante
- réacteur avancé à eau bouillante
Record 1, Spanish
Record 1, Textual support, Spanish
Record 2 - internal organization data 2011-09-19
Record 2, English
Record 2, Subject field(s)
- Nuclear Fission Reactors
Record 2, Main entry term, English
- low void reactivity fuel
1, record 2, English, low%20void%20reactivity%20fuel
correct
Record 2, Abbreviations, English
Record 2, Synonyms, English
Record 2, Textual support, English
Record number: 2, Textual support number: 1 CONT
Low Void Reactivity Fuel(LVRF) involves the implementation of fuel design changes to reduce the positive coolant void reactivity, and as such alleviates the root cause of the problem and therefore enhances the robustness of the Loss of Coolant Accident(LOCA) safety case. 1, record 2, English, - low%20void%20reactivity%20fuel
Record 2, Key term(s)
- low-void reactivity fuel
Record 2, French
Record 2, Domaine(s)
- Réacteurs nucléaires de fission
Record 2, Main entry term, French
- combustible à faible réactivité cavitaire
1, record 2, French, combustible%20%C3%A0%20faible%20r%C3%A9activit%C3%A9%20cavitaire
correct, masculine noun
Record 2, Abbreviations, French
Record 2, Synonyms, French
- combustible à faible coefficient de vide 2, record 2, French, %20combustible%20%C3%A0%20faible%20coefficient%20de%20vide
correct, masculine noun
Record 2, Textual support, French
Record 2, Spanish
Record 2, Textual support, Spanish
Record 3 - external organization data 2011-02-23
Record 3, English
Record 3, Subject field(s)
- Nuclear Power Stations
- Nuclear Fission Reactors
- Compartment - Canadian Nuclear Safety Commission
Record 3, Main entry term, English
- loss-of-coolant accident
1, record 3, English, loss%2Dof%2Dcoolant%20accident
correct, standardized
Record 3, Abbreviations, English
- LOCA 2, record 3, English, LOCA
correct, standardized
Record 3, Synonyms, English
- loss of coolant accident 3, record 3, English, loss%20of%20coolant%20accident
correct
- LOCA 4, record 3, English, LOCA
correct
- LOCA 4, record 3, English, LOCA
Record 3, Textual support, English
Record number: 3, Textual support number: 1 DEF
An accident in which the primary coolant of a nuclear reactor is lost at a rate that exceeds the capability of the make-up system. [Definition standardized by ISO.] 2, record 3, English, - loss%2Dof%2Dcoolant%20accident
Record number: 3, Textual support number: 1 CONT
In the event of a loss-of-coolant accident, the emergency core cooling system maintains the temperature of the fuel at a safe level, preventing rupture of the fuel sheaths and the release of activity. 5, record 3, English, - loss%2Dof%2Dcoolant%20accident
Record number: 3, Textual support number: 1 OBS
Applies to CANDU nuclear reactors. 6, record 3, English, - loss%2Dof%2Dcoolant%20accident
Record number: 3, Textual support number: 2 OBS
loss-of-coolant accident; LOCA : term and abbreviation standardized by ISO. 7, record 3, English, - loss%2Dof%2Dcoolant%20accident
Record 3, Key term(s)
- L.O.C.A.
Record 3, French
Record 3, Domaine(s)
- Centrales nucléaires
- Réacteurs nucléaires de fission
- Tiroir - Commission canadienne de sûreté nucléaire
Record 3, Main entry term, French
- accident de perte de réfrigérant primaire
1, record 3, French, accident%20de%20perte%20de%20r%C3%A9frig%C3%A9rant%20primaire
correct, masculine noun, standardized
Record 3, Abbreviations, French
- APRP 2, record 3, French, APRP
correct, masculine noun, standardized
Record 3, Synonyms, French
- accident de perte du réfrigérant primaire 3, record 3, French, accident%20de%20perte%20du%20r%C3%A9frig%C3%A9rant%20primaire
correct, masculine noun
- accident de perte de réfrigérant 4, record 3, French, accident%20de%20perte%20de%20r%C3%A9frig%C3%A9rant
correct, masculine noun
- accident de perte de caloporteur 5, record 3, French, accident%20de%20perte%20de%20caloporteur
correct, masculine noun
- perte de caloporteur 6, record 3, French, perte%20de%20caloporteur
avoid, feminine noun
- PERCA 6, record 3, French, PERCA
avoid, feminine noun
- PERCA 6, record 3, French, PERCA
Record 3, Textual support, French
Record number: 3, Textual support number: 1 DEF
Accident dans lequel le fluide primaire de refroidissement d'un réacteur nucléaire est perdu avec un débit qui dépasse les possibilités du système d'appoint. [Définition normalisée par l'ISO.] 7, record 3, French, - accident%20de%20perte%20de%20r%C3%A9frig%C3%A9rant%20primaire
Record number: 3, Textual support number: 1 CONT
L'accident de perte du réfrigérant primaire. [...] la rupture du circuit primaire [...] risque de mettre en cause l'intégrité des gaines [...] dont le refroidissement n'est plus assuré de façon normale alors que le coeur du réacteur continue à dégager une puissance résiduelle importante [...] 3, record 3, French, - accident%20de%20perte%20de%20r%C3%A9frig%C3%A9rant%20primaire
Record number: 3, Textual support number: 1 OBS
accident de perte de réfrigérant primaire; APRP : terme et abréviation normalisés par l'ISO. 7, record 3, French, - accident%20de%20perte%20de%20r%C3%A9frig%C3%A9rant%20primaire
Record 3, Spanish
Record 3, Textual support, Spanish
Record 4 - internal organization data 2011-02-08
Record 4, English
Record 4, Subject field(s)
- Nuclear Fission Reactors
Record 4, Main entry term, English
- primary containment
1, record 4, English, primary%20containment
correct
Record 4, Abbreviations, English
Record 4, Synonyms, English
Record 4, Textual support, English
Record number: 4, Textual support number: 1 DEF
In a PWR [pressurized water reactor], a large thick reinforced or prestressed concrete or steel enclosure surrounding the reactor system and capable of withstanding the pressures and temperatures caused by a LOCA [loss of coolant accident]. 1, record 4, English, - primary%20containment
Record 4, French
Record 4, Domaine(s)
- Réacteurs nucléaires de fission
Record 4, Main entry term, French
- enceinte de confinement primaire
1, record 4, French, enceinte%20de%20confinement%20primaire
correct, feminine noun
Record 4, Abbreviations, French
Record 4, Synonyms, French
- enceinte primaire 2, record 4, French, enceinte%20primaire
feminine noun
Record 4, Textual support, French
Record number: 4, Textual support number: 1 DEF
Dans un REP [réacteur à eau sous pression], grande enceinte aux épaisses parois (béton armé, précontraint ou acier) enveloppant le réacteur et capable de résister aux pressions et températures causées par un accident de perte de réfrigérant. 1, record 4, French, - enceinte%20de%20confinement%20primaire
Record 4, Spanish
Record 4, Textual support, Spanish
Record 5 - internal organization data 2011-01-13
Record 5, English
Record 5, Subject field(s)
- Nuclear Fission Reactors
Record 5, Main entry term, English
- moisture separator/dryer
1, record 5, English, moisture%20separator%2Fdryer
correct
Record 5, Abbreviations, English
Record 5, Synonyms, English
Record 5, Textual support, English
Record number: 5, Textual support number: 1 CONT
moisture separator/dryer. The upper surface of [the] ceiling is commonly the refueling floor of [the] reactor building. A hatch standing above the PCC [passive containment cooling] heat exchanger has a cover … which is removable to allow access to PCC heat exchanger for servicing. During operation following a LOCA [loss-of-coolant accident], as heat is conducted out of [the] PCC heat exchanger, secondary steam formed in [the] pool chamber flows through [the] airspace and passes through [the] moisture separator/dryer unit and then through [the] outlet piping to reach the environs outside [the] reactor building. 2, record 5, English, - moisture%20separator%2Fdryer
Record 5, Key term(s)
- moisture separator dryer
- moisture separator-dryer
Record 5, French
Record 5, Domaine(s)
- Réacteurs nucléaires de fission
Record 5, Main entry term, French
- séparateur-sécheur
1, record 5, French, s%C3%A9parateur%2Ds%C3%A9cheur
correct, masculine noun
Record 5, Abbreviations, French
Record 5, Synonyms, French
Record 5, Textual support, French
Record number: 5, Textual support number: 1 CONT
[Réacteurs à eau sous pression.] La partie secondaire des GV [générateurs de vapeur] étant à une pression plus faible que celle de la partie primaire, l’eau d’alimentation secondaire des GV est chauffée jusqu’à saturation puis vaporisée. La vapeur est séchée soit par passage dans des séparateurs-sécheurs, soit par surchauffe, avant d’être envoyée vers la turbine. 2, record 5, French, - s%C3%A9parateur%2Ds%C3%A9cheur
Record 5, Key term(s)
- séparateur sécheur
Record 5, Spanish
Record 5, Textual support, Spanish
Record 6 - internal organization data 2010-12-07
Record 6, English
Record 6, Subject field(s)
- Cooling and Ventilating Systems
- Nuclear Fission Reactors
Record 6, Main entry term, English
- integrated primary coolant system
1, record 6, English, integrated%20primary%20coolant%20system
correct
Record 6, Abbreviations, English
Record 6, Synonyms, English
Record 6, Textual support, English
Record number: 6, Textual support number: 1 CONT
Integrated primary coolant system, eliminating large-break LOCA [loss-of-coolant accident]. 1, record 6, English, - integrated%20primary%20coolant%20system
Record 6, French
Record 6, Domaine(s)
- Systèmes de refroidissement et de ventilation
- Réacteurs nucléaires de fission
Record 6, Main entry term, French
- circuit primaire intégré
1, record 6, French, circuit%20primaire%20int%C3%A9gr%C3%A9
correct, masculine noun
Record 6, Abbreviations, French
Record 6, Synonyms, French
Record 6, Textual support, French
Record number: 6, Textual support number: 1 CONT
[Réacteurs à neutrons rapides refroidis au sodium.] Le circuit primaire peut être disposé suivant deux grandes familles : circuit primaire intégré […] entièrement contenu à l’intérieur de la cuve renfermant le cœur : les pompes primaires et les échangeurs intermédiaires plongent dans le sodium de la cuve principale, à travers la dalle de fermeture de cette cuve; circuit primaire à boucles […] 1, record 6, French, - circuit%20primaire%20int%C3%A9gr%C3%A9
Record 6, Spanish
Record 6, Textual support, Spanish
Record 7 - internal organization data 2009-10-29
Record 7, English
Record 7, Subject field(s)
- Cooling and Ventilating Systems
- Nuclear Fission Reactors
Record 7, Main entry term, English
- long-term cooling system
1, record 7, English, long%2Dterm%20cooling%20system
correct
Record 7, Abbreviations, English
Record 7, Synonyms, English
- LTC system 1, record 7, English, LTC%20system
correct
Record 7, Textual support, English
Record number: 7, Textual support number: 1 CONT
Long-term cooling(LTC) system : The LTC system provides long-term recirculation and recovery. It is used for cooling of the reactor after postulated transients, including LOCA, and during maintenance. 1, record 7, English, - long%2Dterm%20cooling%20system
Record 7, French
Record 7, Domaine(s)
- Systèmes de refroidissement et de ventilation
- Réacteurs nucléaires de fission
Record 7, Main entry term, French
- circuit de refroidissement à long terme
1, record 7, French, circuit%20de%20refroidissement%20%C3%A0%20long%20terme
masculine noun
Record 7, Abbreviations, French
Record 7, Synonyms, French
- circuit LTC 1, record 7, French, circuit%20LTC
masculine noun
Record 7, Textual support, French
Record number: 7, Textual support number: 1 CONT
Circuit de refroidissement à long terme (LTC) : le circuit LTC est chargé de la recirculation et de la récupération à long terme. Il permet de refroidir le réacteur après d'hypothétiques transitoires, y compris une PERCA, et pendant les opérations de maintenance. Il redémarre automatiquement lorsque le circuit primaire est suffisamment dépressurisé, après quoi il passe au mode de récupération à long terme. 1, record 7, French, - circuit%20de%20refroidissement%20%C3%A0%20long%20terme
Record 7, Spanish
Record 7, Textual support, Spanish
Record 8 - internal organization data 2009-10-07
Record 8, English
Record 8, Subject field(s)
- Nuclear Plant Safety
- Nuclear Fission Reactors
Record 8, Main entry term, English
- high pressure safety injection
1, record 8, English, high%20pressure%20safety%20injection
correct
Record 8, Abbreviations, English
- HPSI 1, record 8, English, HPSI
correct
Record 8, Synonyms, English
Record 8, Textual support, English
Record number: 8, Textual support number: 1 DEF
A safety system designed to provide small quantities of high pressure water to keep the fuel in the reactor covered in the event of a small-break LOCA [Loss of Coolant Accident]. 1, record 8, English, - high%20pressure%20safety%20injection
Record 8, French
Record 8, Domaine(s)
- Sûreté des centrales nucléaires
- Réacteurs nucléaires de fission
Record 8, Main entry term, French
- injection de sécurité haute pression
1, record 8, French, injection%20de%20s%C3%A9curit%C3%A9%20haute%20pression
correct, feminine noun
Record 8, Abbreviations, French
Record 8, Synonyms, French
Record 8, Textual support, French
Record number: 8, Textual support number: 1 CONT
Mise en service de l'injection de sécurité haute pression. 1, record 8, French, - injection%20de%20s%C3%A9curit%C3%A9%20haute%20pression
Record 8, Spanish
Record 8, Textual support, Spanish
Record 9 - external organization data 2008-07-02
Record 9, English
Record 9, Subject field(s)
- Industrial Standardization
- Nuclear Power Stations
- Compartment - Canadian Nuclear Safety Commission
Record 9, Main entry term, English
- nuclear industry standard code 1, record 9, English, nuclear%20industry%20standard%20code
Record 9, Abbreviations, English
Record 9, Synonyms, English
Record 9, Textual support, English
Record number: 9, Textual support number: 1 CONT
The nuclear industry standard codes for modelling fuel behaviour during normal operation and a LOCA [loss of coolant accident] or LOR [loss of regulation] event are based on a 1D axi-symmetric model of a fuel element, in which the end cap is not modelled in detail. 1, record 9, English, - nuclear%20industry%20standard%20code
Record 9, French
Record 9, Domaine(s)
- Normalisation industrielle
- Centrales nucléaires
- Tiroir - Commission canadienne de sûreté nucléaire
Record 9, Main entry term, French
- code de normalisation de l'industrie nucléaire
1, record 9, French, code%20de%20normalisation%20de%20l%27industrie%20nucl%C3%A9aire
masculine noun
Record 9, Abbreviations, French
Record 9, Synonyms, French
Record 9, Textual support, French
Record number: 9, Textual support number: 1 CONT
Les codes de normalisation de l'industrie nucléaire pour la modélisation du comportement du combustible durant l'exploitation normale et lors d'un APRP [accident de perte de réfrigérant primaire] ou d'une PCR [perte de contrôle de la réactivité] sont fondés sur un modèle axisymétrique des éléments de combustible, dans lequel le bouchon d'extrémité n'est pas modélisé de manière détaillée. 1, record 9, French, - code%20de%20normalisation%20de%20l%27industrie%20nucl%C3%A9aire
Record 9, Spanish
Record 9, Textual support, Spanish
Record 10 - external organization data 2007-11-08
Record 10, English
Record 10, Subject field(s)
- Nuclear Fission Reactors
- Compartment - Canadian Nuclear Safety Commission
Record 10, Main entry term, English
- axial expansion 1, record 10, English, axial%20expansion
Record 10, Abbreviations, English
Record 10, Synonyms, English
Record 10, Textual support, English
Record number: 10, Textual support number: 1 CONT
Constrained axial expansion of the fuel string within a CANDU fuel channel is typically associated with fuel heatup after a large break LOCA [loss of coolant accident] or a fast LOR [loss of regulation]. 1, record 10, English, - axial%20expansion
Record 10, French
Record 10, Domaine(s)
- Réacteurs nucléaires de fission
- Tiroir - Commission canadienne de sûreté nucléaire
Record 10, Main entry term, French
- dilatation axiale
1, record 10, French, dilatation%20axiale
feminine noun
Record 10, Abbreviations, French
Record 10, Synonyms, French
Record 10, Textual support, French
Record number: 10, Textual support number: 1 CONT
La dilatation axiale sous contrainte du chapelet de grappes de combustible dans un canal de combustible CANDU est habituellement associée à une surchauffe du combustible après un APRP [accident de perte de réfrigérant primaire] dû à une grosse brèche, ou après une perte rapide de contrôle de la réactivité (PCR). 1, record 10, French, - dilatation%20axiale
Record 10, Spanish
Record 10, Textual support, Spanish
Record 11 - external organization data 2007-11-08
Record 11, English
Record 11, Subject field(s)
- Nuclear Fission Reactors
- Nuclear Power Stations
- Compartment - Canadian Nuclear Safety Commission
Record 11, Main entry term, English
- fuel behaviour 1, record 11, English, fuel%20behaviour
Record 11, Abbreviations, English
Record 11, Synonyms, English
Record 11, Textual support, English
Record number: 11, Textual support number: 1 CONT
The nuclear industry standard codes for modelling fuel behaviour during normal operation and a LOCA [loss of coolant accident] or LOR [loss of regulation] event are based on a 1D axi-symmetric model of a fuel element, in which the end cap is not modelled in detail. 1, record 11, English, - fuel%20behaviour
Record 11, French
Record 11, Domaine(s)
- Réacteurs nucléaires de fission
- Centrales nucléaires
- Tiroir - Commission canadienne de sûreté nucléaire
Record 11, Main entry term, French
- comportement du combustible
1, record 11, French, comportement%20du%20combustible
masculine noun
Record 11, Abbreviations, French
Record 11, Synonyms, French
Record 11, Textual support, French
Record number: 11, Textual support number: 1 CONT
Les codes de normalisation de l'industrie du nucléaire pour la modélisation du comportement du combustible durant l'exploitation normale et lors d'un APRP [accident de perte de réfrigérant primaire] ou d'une PCR [perte de contrôle de la réactivité] sont fondés sur un modèle axisymétrique des éléments de combustible, dans lequel le bouchon d'extrémité n'est pas modélisé de manière détaillée. 1, record 11, French, - comportement%20du%20combustible
Record 11, Spanish
Record 11, Textual support, Spanish
Record 12 - external organization data 2007-11-08
Record 12, English
Record 12, Subject field(s)
- Nuclear Power Stations
- Compartment - Canadian Nuclear Safety Commission
Record 12, Main entry term, English
- fuel heatup 1, record 12, English, fuel%20heatup
Record 12, Abbreviations, English
Record 12, Synonyms, English
Record 12, Textual support, English
Record number: 12, Textual support number: 1 CONT
Constrained axial expansion of the fuel string within a CANDU fuel channel is typically associated with fuel heatup after a large break LOCA [large loss of coolant accident] or a fast LOR. 1, record 12, English, - fuel%20heatup
Record 12, French
Record 12, Domaine(s)
- Centrales nucléaires
- Tiroir - Commission canadienne de sûreté nucléaire
Record 12, Main entry term, French
- surchauffe du combustible
1, record 12, French, surchauffe%20du%20combustible
feminine noun
Record 12, Abbreviations, French
Record 12, Synonyms, French
Record 12, Textual support, French
Record number: 12, Textual support number: 1 CONT
La dilatation axiale sous contrainte du chapelet de grappes de combustible dans un canal de combustible CANDU est habituellement associée à une surchauffe du combustible après un APRP [accident grave de perte de réfrigérant primaire] dû à une grosse brèche, ou après une perte rapide de contrôle de la réactivité (PCR). 1, record 12, French, - surchauffe%20du%20combustible
Record 12, Spanish
Record 12, Textual support, Spanish
Record 13 - external organization data 2007-11-08
Record 13, English
Record 13, Subject field(s)
- Modelling (Mathematics)
- Nuclear Fission Reactors
- Compartment - Canadian Nuclear Safety Commission
Record 13, Main entry term, English
- axi-symmetric model 1, record 13, English, axi%2Dsymmetric%20model
Record 13, Abbreviations, English
Record 13, Synonyms, English
Record 13, Textual support, English
Record number: 13, Textual support number: 1 CONT
The nuclear industry standard codes for modelling fuel behaviour during normal operation and a LOCA [loss of coolant accident] or LOR [loss of regulation] event are based on a 1D axi-symmetric model of a fuel element, in which the end cap is not modelled in detail. 1, record 13, English, - axi%2Dsymmetric%20model
Record 13, French
Record 13, Domaine(s)
- Modélisation (Mathématique)
- Réacteurs nucléaires de fission
- Tiroir - Commission canadienne de sûreté nucléaire
Record 13, Main entry term, French
- modèle axisymétrique
1, record 13, French, mod%C3%A8le%20axisym%C3%A9trique
masculine noun
Record 13, Abbreviations, French
Record 13, Synonyms, French
Record 13, Textual support, French
Record number: 13, Textual support number: 1 CONT
Les codes de normalisation de l'industrie du nucléaire pour la modélisation du comportement du combustible durant l'exploitation normale et lors d'un APRP [accident de perte de réfrigérant primaire] ou d'une PCR [perte de contrôle de la réactivité] sont fondés sur un modèle axisymétrique des éléments de combustible, dans lequel le bouchon d'extrémité n'est pas modélisé de manière détaillée. 1, record 13, French, - mod%C3%A8le%20axisym%C3%A9trique
Record 13, Spanish
Record 13, Textual support, Spanish
Record 14 - external organization data 2006-01-24
Record 14, English
Record 14, Subject field(s)
- Nuclear Plant Safety
- Thermodynamics
- Compartment - Canadian Nuclear Safety Commission
Record 14, Main entry term, English
- emergency coolant injection system 1, record 14, English, emergency%20coolant%20injection%20system
Record 14, Abbreviations, English
Record 14, Synonyms, English
- ECI system 1, record 14, English, ECI%20system
Record 14, Textual support, English
Record number: 14, Textual support number: 1 CONT
The emergency coolant injection system(ECIS) protects the fuel and heat transport system boundary when normal cooling fails. Its purpose is to refill the heat transport system and keep it full after a loss of coolant accident(LOCA). This sets up an alternative heat flow path for removing decay heat. 1, record 14, English, - emergency%20coolant%20injection%20system
Record 14, French
Record 14, Domaine(s)
- Sûreté des centrales nucléaires
- Thermodynamique
- Tiroir - Commission canadienne de sûreté nucléaire
Record 14, Main entry term, French
- système d'injection d'urgence du caloporteur
1, record 14, French, syst%C3%A8me%20d%27injection%20d%27urgence%20du%20caloporteur
masculine noun
Record 14, Abbreviations, French
Record 14, Synonyms, French
- système de refroidissement d'urgence du coeur par injection 1, record 14, French, syst%C3%A8me%20de%20refroidissement%20d%27urgence%20du%20coeur%20par%20injection
masculine noun
- SRUCI 1, record 14, French, SRUCI
masculine noun
- SRUCI 1, record 14, French, SRUCI
- système de refroidissement d'urgence du coeur 1, record 14, French, syst%C3%A8me%20de%20refroidissement%20d%27urgence%20du%20coeur
masculine noun
- SRUC 1, record 14, French, SRUC
masculine noun
- SRUC 1, record 14, French, SRUC
Record 14, Textual support, French
Record number: 14, Textual support number: 1 CONT
Le système de refroidissement d'urgence du coeur par injection (SRUCI) protège le combustible et la limite du circuit caloporteur lorsque le refroidissement normal subit une défaillance. Il a pour but de remplir le circuit caloporteur et de le maintenir plein après un accident dû à la perte de réfrigérant primaire (APRP). Cela constitue un autre trajet pour le flux de chaleur qui élimine la chaleur de désintégration. 1, record 14, French, - syst%C3%A8me%20d%27injection%20d%27urgence%20du%20caloporteur
Record 14, Spanish
Record 14, Textual support, Spanish
Record 15 - internal organization data 1997-11-11
Record 15, English
Record 15, Subject field(s)
- Meetings
Record 15, Main entry term, English
- Specialists Meeting on Small Break Loca Analyses in LWRs 1, record 15, English, Specialists%20Meeting%20on%20Small%20Break%20Loca%20Analyses%20in%20LWRs
Record 15, Abbreviations, English
Record 15, Synonyms, English
Record 15, Textual support, English
Record number: 15, Textual support number: 1 OBS
IAEA [International Atomic Energy Agency]; Pisa, 23-27 June 1985 1, record 15, English, - Specialists%20Meeting%20on%20Small%20Break%20Loca%20Analyses%20in%20LWRs
Record 15, French
Record 15, Domaine(s)
- Réunions
Record 15, Main entry term, French
- Réunion de spécialistes sur les analyses d'APRP
1, record 15, French, R%C3%A9union%20de%20sp%C3%A9cialistes%20sur%20les%20analyses%20d%27APRP
feminine noun
Record 15, Abbreviations, French
Record 15, Synonyms, French
Record 15, Textual support, French
Record 15, Spanish
Record 15, Campo(s) temático(s)
- Reuniones
Record 15, Main entry term, Spanish
- Reunión de especialistas en análisis de accidentes con pérdida de refrigerante
1, record 15, Spanish, Reuni%C3%B3n%20de%20especialistas%20en%20an%C3%A1lisis%20de%20accidentes%20con%20p%C3%A9rdida%20de%20refrigerante
feminine noun
Record 15, Abbreviations, Spanish
Record 15, Synonyms, Spanish
Record 15, Textual support, Spanish
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