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FR2356195A1 - Circuit de refroidissement de securite notamment pour reacteurs nucleaires - Google Patents

Circuit de refroidissement de securite notamment pour reacteurs nucleaires

Info

Publication number
FR2356195A1
FR2356195A1 FR7619363A FR7619363A FR2356195A1 FR 2356195 A1 FR2356195 A1 FR 2356195A1 FR 7619363 A FR7619363 A FR 7619363A FR 7619363 A FR7619363 A FR 7619363A FR 2356195 A1 FR2356195 A1 FR 2356195A1
Authority
FR
France
Prior art keywords
level
siphon
esp
incorporates
receiver
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
FR7619363A
Other languages
English (en)
Other versions
FR2356195B1 (fr
Inventor
Jacques Baujat
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Priority to FR7619363A priority Critical patent/FR2356195A1/fr
Publication of FR2356195A1 publication Critical patent/FR2356195A1/fr
Application granted granted Critical
Publication of FR2356195B1 publication Critical patent/FR2356195B1/fr
Granted legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G05—CONTROLLING; REGULATING
    • G05D—SYSTEMS FOR CONTROLLING OR REGULATING NON-ELECTRIC VARIABLES
    • G05D9/00—Level control, e.g. controlling quantity of material stored in vessel
    • G05D9/02—Level control, e.g. controlling quantity of material stored in vessel without auxiliary power
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Physics & Mathematics (AREA)
  • Automation & Control Theory (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

Dispositif pour maintenir à un niveau N0 sensiblement constant un liquide placé dans un récipient, ledit liquide étant susceptible de se vaporiser sous l'action d'un apport de chaleur audit récipient. Le dispositif comprend des moyens de mise en communication pour mettre en communication l'extrémité supérieure dudit récipient avec ladite enceinte, et une capacité etanche reliée d'une part par une canalisation audit récipient en un point situé en-dessous du niveau à maintenir N0 et d'autre part à une première branche d'un siphon situé sensiblement au niveau N0, la deuxième branche dudit siphon débouchant dans ladite enceinte à un niveau supérieur au niveau N0 . Application au refroidissement de secours de réacteurs à eau sous pression.
FR7619363A 1976-06-25 1976-06-25 Circuit de refroidissement de securite notamment pour reacteurs nucleaires Granted FR2356195A1 (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR7619363A FR2356195A1 (fr) 1976-06-25 1976-06-25 Circuit de refroidissement de securite notamment pour reacteurs nucleaires

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7619363A FR2356195A1 (fr) 1976-06-25 1976-06-25 Circuit de refroidissement de securite notamment pour reacteurs nucleaires

Publications (2)

Publication Number Publication Date
FR2356195A1 true FR2356195A1 (fr) 1978-01-20
FR2356195B1 FR2356195B1 (fr) 1978-12-22

Family

ID=9174862

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7619363A Granted FR2356195A1 (fr) 1976-06-25 1976-06-25 Circuit de refroidissement de securite notamment pour reacteurs nucleaires

Country Status (1)

Country Link
FR (1) FR2356195A1 (fr)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0108044A3 (en) * 1982-09-20 1984-10-17 Universite Catholique De Louvain Cooling water flow regulating apparatus for coal gasification wells
EP0509923A1 (fr) * 1991-04-17 1992-10-21 Framatome Réacteur nucléaire refroidi par de l'eau sous pression comportant un dispositif de vidange du circuit primaire à sécurité intrinsèque à niveau bas déterminé
WO2004093093A3 (fr) * 2003-04-16 2005-01-06 Framatome Anp Gmbh Installation nucleaire et procede d'exploitation d'une installation nucleaire

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0108044A3 (en) * 1982-09-20 1984-10-17 Universite Catholique De Louvain Cooling water flow regulating apparatus for coal gasification wells
EP0509923A1 (fr) * 1991-04-17 1992-10-21 Framatome Réacteur nucléaire refroidi par de l'eau sous pression comportant un dispositif de vidange du circuit primaire à sécurité intrinsèque à niveau bas déterminé
FR2675618A1 (fr) * 1991-04-17 1992-10-23 Framatome Sa Dispositif de vidange du circuit primaire d'un reacteur nucleaire refroidi par de l'eau sous pression a securite intrinseque de niveau bas.
WO2004093093A3 (fr) * 2003-04-16 2005-01-06 Framatome Anp Gmbh Installation nucleaire et procede d'exploitation d'une installation nucleaire

Also Published As

Publication number Publication date
FR2356195B1 (fr) 1978-12-22

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Legal Events

Date Code Title Description
ST Notification of lapse