FR2310612A1 - Primary coolant circuit for nuclear reactor - has pumps mounted below heat exchangers in a separate vessel in which output from pumps is mixed - Google Patents

Primary coolant circuit for nuclear reactor - has pumps mounted below heat exchangers in a separate vessel in which output from pumps is mixed

Info

Publication number
FR2310612A1
FR2310612A1 FR7514171A FR7514171A FR2310612A1 FR 2310612 A1 FR2310612 A1 FR 2310612A1 FR 7514171 A FR7514171 A FR 7514171A FR 7514171 A FR7514171 A FR 7514171A FR 2310612 A1 FR2310612 A1 FR 2310612A1
Authority
FR
France
Prior art keywords
pumps
vessel
mixed
exchangers
nuclear reactor
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
FR7514171A
Other languages
French (fr)
Other versions
FR2310612B1 (en
Inventor
Pierre Fradin
Gilbert Martin
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.)
Cegelec SA
Original Assignee
Cegelec SA
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 Cegelec SA filed Critical Cegelec SA
Priority to FR7514171A priority Critical patent/FR2310612A1/en
Publication of FR2310612A1 publication Critical patent/FR2310612A1/en
Application granted granted Critical
Publication of FR2310612B1 publication Critical patent/FR2310612B1/fr
Granted legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/04—Pumping arrangements
    • 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

Abstract

A nuclear reactor has a first vessel contg. the reactor core and the primary heat transport fluid, a second vessel contg. the heat exchanger and pumps driven by motors outside the vessel for the circulation of primary fluid through the exchanger. The primary fluid circulating pumps are located at one end of the exchangers. The output flow from several exchangers are mixed in the second vessel before passing to the suction of the pumps for delivering to the first vessel. Pref. the circulation pumps are located below and coaxially with the exchangers. Permits the size of the second vessel to be reduced, as well as the number of apertures in the cover for the removal of the heat exchangers and/or pumps and the size of the handling equipment required for this purpose.
FR7514171A 1975-05-06 1975-05-06 Primary coolant circuit for nuclear reactor - has pumps mounted below heat exchangers in a separate vessel in which output from pumps is mixed Granted FR2310612A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR7514171A FR2310612A1 (en) 1975-05-06 1975-05-06 Primary coolant circuit for nuclear reactor - has pumps mounted below heat exchangers in a separate vessel in which output from pumps is mixed

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7514171A FR2310612A1 (en) 1975-05-06 1975-05-06 Primary coolant circuit for nuclear reactor - has pumps mounted below heat exchangers in a separate vessel in which output from pumps is mixed

Publications (2)

Publication Number Publication Date
FR2310612A1 true FR2310612A1 (en) 1976-12-03
FR2310612B1 FR2310612B1 (en) 1977-12-09

Family

ID=9154915

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7514171A Granted FR2310612A1 (en) 1975-05-06 1975-05-06 Primary coolant circuit for nuclear reactor - has pumps mounted below heat exchangers in a separate vessel in which output from pumps is mixed

Country Status (1)

Country Link
FR (1) FR2310612A1 (en)

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1449917A (en) * 1965-07-09 1966-05-06 Soc Indatom Heat extraction device and nuclear reactor comprising such a device

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1449917A (en) * 1965-07-09 1966-05-06 Soc Indatom Heat extraction device and nuclear reactor comprising such a device

Also Published As

Publication number Publication date
FR2310612B1 (en) 1977-12-09

Similar Documents

Publication Publication Date Title
GB1481544A (en) Sodium-cooled fast reactor having a device for the removal of residual heat
FR2296248A1 (en) Nuclear reactor fuelled by eutectic salt mixture - with integral primary cooling system
GB792171A (en) Improvements in heat removal systems for nuclear reactors
DK136558B (en) Method for increasing the circulation of the coolant in a pressure vessel of an atomic core reactor with natural circulation of the coolant in the pressure vessel using a jet pump.
ES417645A1 (en) Nuclear reactor
FR2310612A1 (en) Primary coolant circuit for nuclear reactor - has pumps mounted below heat exchangers in a separate vessel in which output from pumps is mixed
GB1442157A (en) Nuclear power plant with closed gas cooling circuit
GB1150777A (en) Boiling-Water Reactor with Forced Circulation of the Coolant
FR2314559A1 (en) NUCLEAR INSTALLATION
GB885885A (en) Improvements in or relating to nuclear reactors
ES425437A1 (en) Protection system for a nuclear reactor
ES352047A1 (en) Liquid-cooled nuclear reactor
GB1291008A (en)
GB1336716A (en) Emergency cooling system for a nuclear reactor
GB1101067A (en) Improvements in or relating to metal-lined concrete pressure vessels
JPS57100710A (en) Evaporation cooling type induction device
FR2265152A1 (en) Pressure water nuclear reactor - with external heat exchangers and pumps for use as steam generator on a ship
GB1232959A (en)
GB966743A (en) Improvements in nuclear power plant
GB1144172A (en) Improvements in or relating to power plant
FR2041724A1 (en) Gas circuit for gas cooled nuclear reactor
JPS5310805A (en) Superconductive rotor
JPS5648110A (en) Superconductive aparatus
FR2212612A1 (en) Light water cooled nuclear reactor - has a tritium extraction unit in coolant system
FR2132572A1 (en) Gas cooled reactor - with core and primary coolant circuit incorporated in concrete pressure vessel

Legal Events

Date Code Title Description
ST Notification of lapse