GB1434384A - Gas-cooled nuclear reactor installations - Google Patents

Gas-cooled nuclear reactor installations

Info

Publication number
GB1434384A
GB1434384A GB3313473A GB3313473A GB1434384A GB 1434384 A GB1434384 A GB 1434384A GB 3313473 A GB3313473 A GB 3313473A GB 3313473 A GB3313473 A GB 3313473A GB 1434384 A GB1434384 A GB 1434384A
Authority
GB
United Kingdom
Prior art keywords
vessel
tank
steam
core
water
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
GB3313473A
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.)
Siemens AG
Original Assignee
Siemens AG
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 Siemens AG filed Critical Siemens AG
Publication of GB1434384A publication Critical patent/GB1434384A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/016Core catchers
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear 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

1434384 Nuclear reactors SIEMENS AG 11 July 1973 [14 July 1972] 33134/73 Heading G6C In a nuclear reactor installation, a spray system has outlets within the reactor pressure vessel for the purpose of cooling melted core material. The reactor is a gas- (e.g. helium) cooled fast breeder. In one embodiment (Fig. 1) fuel elements are secured by means of a holding device 10 comprising tubes 12 through which coolant gas normally is fed towards the core 4. The coolant circulates within the concrete pressure vessel 2, as indicated by arrows 16, so as to pass in heatexchange relation with a steam-generator 15. The lower part of the shield 3 within the vessel 2 forms a tank 20 which receives core material, should this fuse, and prevents accumulation of a critical size. Water is sprayed into the vessel 2 via the tubes 12 in the event of core meltdown, the steam generated passing to the generator 15; a one-way valve ensures continuance of the (arrowed) flow pattern. A larger tank 25 is provided to receive debris should the core melt its way through the base of tank 20 and the vessel wall supporting the latter; additional cooling means may be provided in tank 25. Should steam not be routed through the steamgenerator 15 as described, it may be released into the interior of the steel containment 1 and heat removed therefrom by water emanating from an external sprinkler system 28. In another embodiment (Fig. 2) water can be sprayed into tank 20 from lines 30, 31 within the vessel 2. After passing through the steamgenerator 15, excess steam can pass to the exterior of the vessel 2 via an aperture 36 to give up heat to the surrounding steel containment.
GB3313473A 1972-07-14 1973-07-11 Gas-cooled nuclear reactor installations Expired GB1434384A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2234744A DE2234744A1 (en) 1972-07-14 1972-07-14 NUCLEAR REACTOR

Publications (1)

Publication Number Publication Date
GB1434384A true GB1434384A (en) 1976-05-05

Family

ID=5850688

Family Applications (1)

Application Number Title Priority Date Filing Date
GB3313473A Expired GB1434384A (en) 1972-07-14 1973-07-11 Gas-cooled nuclear reactor installations

Country Status (4)

Country Link
DE (1) DE2234744A1 (en)
FR (1) FR2193232A1 (en)
GB (1) GB1434384A (en)
IT (1) IT992614B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5930319A (en) * 1995-06-27 1999-07-27 Siemens Aktiengesellschaft Nuclear reactor with a core melt propagation space provided with a coolant conduit leading to a coolant reservoir
CN114728337A (en) * 2019-11-22 2022-07-08 法国电力公司 Solid metal component and method for producing a solid metal component

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2653258C2 (en) * 1976-11-24 1985-02-28 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Process for reducing the dangers that may arise as a result of an accident through the melting of a nuclear reactor core, as well as an arrangement for carrying out the process

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5930319A (en) * 1995-06-27 1999-07-27 Siemens Aktiengesellschaft Nuclear reactor with a core melt propagation space provided with a coolant conduit leading to a coolant reservoir
CN114728337A (en) * 2019-11-22 2022-07-08 法国电力公司 Solid metal component and method for producing a solid metal component

Also Published As

Publication number Publication date
DE2234744A1 (en) 1974-01-31
IT992614B (en) 1975-09-30
FR2193232A1 (en) 1974-02-15

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Legal Events

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