GB1134520A - Improvements relating to nuclear reactors - Google Patents

Improvements relating to nuclear reactors

Info

Publication number
GB1134520A
GB1134520A GB51744/66A GB5174466A GB1134520A GB 1134520 A GB1134520 A GB 1134520A GB 51744/66 A GB51744/66 A GB 51744/66A GB 5174466 A GB5174466 A GB 5174466A GB 1134520 A GB1134520 A GB 1134520A
Authority
GB
United Kingdom
Prior art keywords
steam
reactor
coolant
diffuser
nov
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
GB51744/66A
Inventor
Shepherd Rigg
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB51744/66A priority Critical patent/GB1134520A/en
Publication of GB1134520A publication Critical patent/GB1134520A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/02—Arrangements of auxiliary equipment
    • 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
    • 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
    • G21C15/24—Promoting flow of the coolant
    • 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
    • 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

1,134,520. Reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. 13 Nov., 1967 [18 Nov., 1966], No. 51744/66. Heading G6C. In a pressurized water reactor steam generating system, steam is formed in a vortex-type pressure reduction device external to the reactor. Coolant water from the reactor vessel 1 flows to the vapour generator 5 through duct 4. The drop in pressure at 8 after coolant flow through the coolant chamber 10 causes the generation of steam in the central vortex. Steam is led to the utilization plant through duct 12. Repressurization is induced in the diffuser 9 connected to the return inlet 3. Circulation is maintained by natural convection. The by-pass 6 may accept half the total flow. A make up connection 13 leads to the diffuser 9.
GB51744/66A 1966-11-18 1966-11-18 Improvements relating to nuclear reactors Expired GB1134520A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB51744/66A GB1134520A (en) 1966-11-18 1966-11-18 Improvements relating to nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB51744/66A GB1134520A (en) 1966-11-18 1966-11-18 Improvements relating to nuclear reactors

Publications (1)

Publication Number Publication Date
GB1134520A true GB1134520A (en) 1968-11-27

Family

ID=10461207

Family Applications (1)

Application Number Title Priority Date Filing Date
GB51744/66A Expired GB1134520A (en) 1966-11-18 1966-11-18 Improvements relating to nuclear reactors

Country Status (1)

Country Link
GB (1) GB1134520A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2072017A1 (en) * 1969-12-23 1971-09-24 British Nuclear Design Constr

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2072017A1 (en) * 1969-12-23 1971-09-24 British Nuclear Design Constr

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