GB1173024A - Heat Exchanger Plant for the Exchangeable Media Liquid-Metal/Water - Google Patents

Heat Exchanger Plant for the Exchangeable Media Liquid-Metal/Water

Info

Publication number
GB1173024A
GB1173024A GB08566/67A GB1856667A GB1173024A GB 1173024 A GB1173024 A GB 1173024A GB 08566/67 A GB08566/67 A GB 08566/67A GB 1856667 A GB1856667 A GB 1856667A GB 1173024 A GB1173024 A GB 1173024A
Authority
GB
United Kingdom
Prior art keywords
sodium
water
chamber
heat exchanger
pipe
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
GB08566/67A
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.)
Interatom Internationale Atomreaktorbau GmbH
Original Assignee
Interatom Internationale Atomreaktorbau GmbH
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 Interatom Internationale Atomreaktorbau GmbH filed Critical Interatom Internationale Atomreaktorbau GmbH
Publication of GB1173024A publication Critical patent/GB1173024A/en
Expired legal-status Critical Current

Links

Classifications

    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00—Methods of steam generation characterised by form of heating method
    • F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/06—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium
    • F22B1/063—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium for metal cooled nuclear reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/002—Detection of leaks
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/002—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices against Na- or Ka- reactions
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004—Pressure suppression
    • G21C9/008—Pressure suppression by rupture-discs or -diaphragms
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Chemical & Material Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

1,173,024. Steam generators. INTERATOM, INTERNATIONALE ATOMREAKTORBAU G.m.b.H. 21 April, 1967 [31 May, 1966], No. 18566/67. Heading F4A. [Also in Division G6] In a nuclear power plant, a liquid sodium, water heat exchanger is provided with a backflow restricting device to limit damage due to pipe fracture. Hydrogen bubble detectors are associated with the sodium lines to indicate transfer of hydrogen from the water lines through faults in the pipe walls. Non-return valves in the sodium supply line close when pipe fracture occurs. The sodium, water reaction zone moves through the sodium outlet line to a buffer vessel. A rupture disc in the vessel releases the reaction zone to a transfer chamber from where it moves to a separator. A gas pressurized surge tank is associated with the buffer vessel. Sodium flows from pipe 1 to the discharge line 11, through the outer tube of the exchanger units 8. A liquid sodium, water reaction closes the non-return valve 6, and the hydrogen bubble detectors 40 are located at 11. Water, for steam generation, enters at 12. The cooled sodium enters the buffer chamber 20, isolated by the rupture disc 21 from the chamber 22 and the separator 24. Vapour and gas are evacuated by 25 and metal tapped off at 26. Liquid metal leaves 22 through the orifice 28, and flows into the surge tank 32. After a pipe fracture, the valves 6 close line 3 and the reaction zone moves into chamber 22. Rupture disc 21 fractures and sodium flows to separator 24. The generation of high pressures is prevented by surge tank 32, orifice 28 and the transfer chamber. In modifications an additional buffer chamber is included in the hot side of the sodium circuit and two similar heat exchanger systems may be operated in parallel.
GB08566/67A 1966-05-31 1967-04-21 Heat Exchanger Plant for the Exchangeable Media Liquid-Metal/Water Expired GB1173024A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DEJ0030955 1966-05-31

Publications (1)

Publication Number Publication Date
GB1173024A true GB1173024A (en) 1969-12-03

Family

ID=7204048

Family Applications (1)

Application Number Title Priority Date Filing Date
GB08566/67A Expired GB1173024A (en) 1966-05-31 1967-04-21 Heat Exchanger Plant for the Exchangeable Media Liquid-Metal/Water

Country Status (2)

Country Link
DE (1) DE1501542C3 (en)
GB (1) GB1173024A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2626057A1 (en) * 1988-01-19 1989-07-21 Doryokuro Kakunenryo Protection device for a hose connector of the bellows type
CZ305830B6 (en) * 2014-09-10 2016-03-30 ENERGOVĂťZKUM, spol. s.r.o. Circuit arrangement of steam generator in sodium circuit of fast reactor nuclear facility

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2626057A1 (en) * 1988-01-19 1989-07-21 Doryokuro Kakunenryo Protection device for a hose connector of the bellows type
CZ305830B6 (en) * 2014-09-10 2016-03-30 ENERGOVĂťZKUM, spol. s.r.o. Circuit arrangement of steam generator in sodium circuit of fast reactor nuclear facility

Also Published As

Publication number Publication date
DE1501542B2 (en) 1974-06-20
DE1501542C3 (en) 1975-02-06
DE1501542A1 (en) 1970-03-05

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee