ES340581A1 - Improvements in and relating to a nuclear installation - Google Patents

Improvements in and relating to a nuclear installation

Info

Publication number
ES340581A1
ES340581A1 ES340581A ES340581A ES340581A1 ES 340581 A1 ES340581 A1 ES 340581A1 ES 340581 A ES340581 A ES 340581A ES 340581 A ES340581 A ES 340581A ES 340581 A1 ES340581 A1 ES 340581A1
Authority
ES
Spain
Prior art keywords
casing
pipes
steam
steam generator
circuit
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
ES340581A
Other languages
Spanish (es)
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of ES340581A1 publication Critical patent/ES340581A1/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/10—Means for preventing contamination in the event of leakage, e.g. double wall
    • 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
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
    • G21D5/04—Reactor and engine not structurally combined
    • G21D5/08—Reactor and engine not structurally combined with engine working medium heated in a heat exchanger by the reactor coolant
    • 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)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

A liquid metal cooled reactor is housed within a double-walled casing, small diameter conduits being disposed between the walls of the casing for circulating heating fluid. A primary coolant circuit between the casing and an intermediate heat exchanger consists of pipes which are also double-walled and inside which similar small diameter conduits are disposed. A secondary coolant circuit also of liquid metal extends between the intermediate heat exchanger and a steam generator, and the heating fluid for the casing and the pipes of the primary circuit is formed by steam taken from that raised by an auxiliary steam generator operated to start the steam generator of the secondary circuit. Small diameter conduits through which heating steam circulates are disposed against the walls of the pipes forming the secondary circuit inside a heat insulation enclosing the pipes. Instead of steam, a pressurized inert gas such as nitrogen may be used as the heating fluid, being circulated by a compressor and heated by exchange with steam raised by the auxiliary steam generator. The primary and secondary liquid metal (e.g. sodium) coolants are solid at ordinary temperatures and consequently it is necessary for the casing and coolant circuit pipes to be heated before they are filled. Similarly, it is desirable to keep the metal in the liquid state during the stoppage periods of the reactor.
ES340581A 1966-05-16 1967-05-16 Improvements in and relating to a nuclear installation Expired ES340581A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR61847A FR1506326A (en) 1966-05-16 1966-05-16 Nuclear facility

Publications (1)

Publication Number Publication Date
ES340581A1 true ES340581A1 (en) 1972-01-01

Family

ID=8608803

Family Applications (1)

Application Number Title Priority Date Filing Date
ES340581A Expired ES340581A1 (en) 1966-05-16 1967-05-16 Improvements in and relating to a nuclear installation

Country Status (7)

Country Link
BE (1) BE697934A (en)
CH (1) CH476366A (en)
DE (1) DE1589609B2 (en)
ES (1) ES340581A1 (en)
FR (1) FR1506326A (en)
GB (1) GB1137298A (en)
LU (1) LU53646A1 (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104934080B (en) * 2015-06-26 2017-05-31 上海核工程研究设计院 A kind of pair of main feed system of reactor of nuclear power plant
CN110767332B (en) * 2019-10-14 2022-07-15 哈尔滨工程大学 Passive residual heat removal system for high-temperature heat pipe reactor
CN113266572A (en) * 2021-07-01 2021-08-17 阿特拉斯·科普柯(无锡)压缩机有限公司 Gas compression system

Also Published As

Publication number Publication date
DE1589609B2 (en) 1971-11-25
DE1589609A1 (en) 1970-08-13
GB1137298A (en) 1968-12-18
BE697934A (en) 1967-10-16
CH476366A (en) 1969-07-31
FR1506326A (en) 1967-12-22
LU53646A1 (en) 1967-07-11

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