GB951896A - Improvements in or relating to nuclear reactor plant - Google Patents

Improvements in or relating to nuclear reactor plant

Info

Publication number
GB951896A
GB951896A GB4795/62A GB479562A GB951896A GB 951896 A GB951896 A GB 951896A GB 4795/62 A GB4795/62 A GB 4795/62A GB 479562 A GB479562 A GB 479562A GB 951896 A GB951896 A GB 951896A
Authority
GB
United Kingdom
Prior art keywords
coolant
pressure vessel
circuit
reactor
pump
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.)
Expired
Application number
GB4795/62A
Inventor
Alan Alfred Cooper
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.)
SOC ANGLO BELGE VULCAIN SA
Original Assignee
SOC ANGLO BELGE VULCAIN 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 SOC ANGLO BELGE VULCAIN SA filed Critical SOC ANGLO BELGE VULCAIN SA
Priority to GB4795/62A priority Critical patent/GB951896A/en
Priority to FR923933A priority patent/FR1350228A/en
Publication of GB951896A publication Critical patent/GB951896A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • 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)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

951,896. Nuclear reactors. SOC. ANGLOBELGE VULCAIN S. A. Jan. 29, 1963 [Feb. 7, 1962], No.4795/62. Heading G6C. A nuclear reactor plant employing a pressurised liquid coolant/moderator circulated in a closed flow circuit which makes a pass through a reactor pressure vessel, is provided with a connection communicating the highest point within the pressure vessel with a confined volume containing a constant mass of gas which acts upon the free surface of the coolant/moderator liquid within the pressure vessel, the pressure of the gas being such that at minimum temperature the circuit is maintained in a primed condition. In the arrangement shown coolant/moderator circulates through the reactor core 1 from an inlet 3 to an outlet 4 and then flows through a heat exchanger 7 and pump 6 back to the inlet. The top of the pressure vessel 2 is connected by a small bore pipe 10 to a closed pressuriser compartment 11 for helium gas. In priming the circuit coolant is pumped into the pressure vessel from tank 18 through valve 16a until it reaches the level LWL. Valves 8, 9 and 16a are then closed, the reactor core is fuelled, the control rods are connected to their drives, and the pressure vessel is resealed. Valves in pipes 15a, 15b are opened to connect the pressure vessel and heat exchanger to a vacuum pump 15 which removes air from the circuit. The pressuriser compartment and pressure vessel are filled with helium from a high pressure supply 13, and pumping of the coolant from tank 18 is continued until the pressure vessel contains sufficient coolant to fill the rest of the circuit under cold conditions. Valve 8 is then opened to allow the circuit to fill, valve 9 is opened and pump 6 started; the reactor is started, and at full operating temperature the coolant will rise to the level HWL. When the reactor is shut down the coolant level falls again but the pressure of the helium gas maintains the continuity of the coolant through the whole flow circuit and the pump 6 can be kept running to dissipate shut-down heat. The coolant may be a mixture of light and heavy water.
GB4795/62A 1962-02-07 1962-02-07 Improvements in or relating to nuclear reactor plant Expired GB951896A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB4795/62A GB951896A (en) 1962-02-07 1962-02-07 Improvements in or relating to nuclear reactor plant
FR923933A FR1350228A (en) 1962-02-07 1963-02-06 Nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB4795/62A GB951896A (en) 1962-02-07 1962-02-07 Improvements in or relating to nuclear reactor plant

Publications (1)

Publication Number Publication Date
GB951896A true GB951896A (en) 1964-03-11

Family

ID=9783936

Family Applications (1)

Application Number Title Priority Date Filing Date
GB4795/62A Expired GB951896A (en) 1962-02-07 1962-02-07 Improvements in or relating to nuclear reactor plant

Country Status (1)

Country Link
GB (1) GB951896A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4612158A (en) * 1982-12-24 1986-09-16 Brown Boveri Reaktor Gmbh Process for controlling leaks between the primary and secondary coolant loops of a pressurized water reactor system
US4859401A (en) * 1985-08-14 1989-08-22 Hitachi, Ltd. Nuclear reactor
US6594333B2 (en) * 2001-11-16 2003-07-15 Japan Nuclear Cycle Development Institute Thermal load reducing system for nuclear reactor vessel

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4612158A (en) * 1982-12-24 1986-09-16 Brown Boveri Reaktor Gmbh Process for controlling leaks between the primary and secondary coolant loops of a pressurized water reactor system
US4859401A (en) * 1985-08-14 1989-08-22 Hitachi, Ltd. Nuclear reactor
US6594333B2 (en) * 2001-11-16 2003-07-15 Japan Nuclear Cycle Development Institute Thermal load reducing system for nuclear reactor vessel

Similar Documents

Publication Publication Date Title
US2945794A (en) Neutronic reactor operational method and core system
US9715948B2 (en) Reactor system with a lead-cooled fast reactor
CN107293341A (en) Pool reactor
KR940001175A (en) How to reduce rupture of steam generator pipe with automatic safety device in pressurized water reactor
GB792972A (en) Control of atomic power reactors
GB951896A (en) Improvements in or relating to nuclear reactor plant
GB1177533A (en) Steam Generator for an Atomic Power Generating Plant.
GB878097A (en) Improvements in or relating to neutronic reactor
SU581892A3 (en) Nuclear power plant
CN209045171U (en) Reactor based on ATF fuel
GB897483A (en) Improvements in or relating to nuclear reactors
GB1084255A (en)
GB1491232A (en) Nuclear reactors
SE328062B (en)
US3275524A (en) Boiling coolant reactor with improved recirculation and by-pass control arrangement
CN110849205B (en) Water-cooling constant-pressure liquid supplementing water tank system and application method thereof
JPH0260845B2 (en)
GB962655A (en) Improvements in pressure-generating liquid surge reservoirs adapted for use with or in communication with systems operating with fluid under pressure
GB1336716A (en) Emergency cooling system for a nuclear reactor
US3035993A (en) Reflector control of a boiling water reactor
US2929767A (en) Convection reactor
CN113447401B (en) Water intake connecting pipe multiphase flow test system and method for residual water system of small nuclear reactor
US3130129A (en) Nuclear reactors
US2975957A (en) Diffusion pumps
SU1503047A1 (en) System for emergency cooling of reasearch nuclear reactor