ES350840A1 - A prestressed concrete pressure vessel for nuclear reactors - Google Patents

A prestressed concrete pressure vessel for nuclear reactors

Info

Publication number
ES350840A1
ES350840A1 ES350840A ES350840A ES350840A1 ES 350840 A1 ES350840 A1 ES 350840A1 ES 350840 A ES350840 A ES 350840A ES 350840 A ES350840 A ES 350840A ES 350840 A1 ES350840 A1 ES 350840A1
Authority
ES
Spain
Prior art keywords
jacks
section
sections
pressure vessel
prestressed concrete
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
ES350840A
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 ES350840A1 publication Critical patent/ES350840A1/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
    • G21C13/093—Concrete vessels
    • G21C13/0933—Concrete vessels made of prestressed concrete
    • E—FIXED CONSTRUCTIONS
    • E04—BUILDING
    • E04H—BUILDINGS OR LIKE STRUCTURES FOR PARTICULAR PURPOSES; SWIMMING OR SPLASH BATHS OR POOLS; MASTS; FENCING; TENTS OR CANOPIES, IN GENERAL
    • E04H7/00—Construction or assembling of bulk storage containers employing civil engineering techniques in situ or off the site
    • E04H7/02—Containers for fluids or gases; Supports therefor
    • E04H7/18—Containers for fluids or gases; Supports therefor mainly of concrete, e.g. reinforced concrete, or other stone-like material
    • E04H7/20—Prestressed constructions
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/06—Sealing-plugs
    • 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)
  • Architecture (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Civil Engineering (AREA)
  • Structural Engineering (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Examining Or Testing Airtightness (AREA)
  • Separation Using Semi-Permeable Membranes (AREA)

Abstract

An integral nuclear reactor prestressed concrete pressure vessel is formed in two sections which are relatively displaceable to permit inspection of internal heat exchangers. The upper and lower sections 6, 8 may be separated by the jacks 34 and the section 6 rotated relatively to 8 by jacks 48. The U-section 30 engages the sliding shoes 38 in 34. Prior to disengagement of 6 and 8, the prestressing cables 10, 11 are split by means of the connector sleeve 16. The internal surfaces of 6 and 8 have leak tight membranes 18, 20, heat insulating lining 22 and coolant circulating system 24. In an alternative form, the vessel sections are first separated, by jacks, and the upper section is then moved laterally away from the lower section on two integral parallel tracks, by separate jacks.
ES350840A 1967-02-24 1968-02-23 A prestressed concrete pressure vessel for nuclear reactors Expired ES350840A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR96492A FR1538984A (en) 1967-02-24 1967-02-24 Opening casing, in prestressed concrete, for a nuclear reactor with integrated heat exchangers

Publications (1)

Publication Number Publication Date
ES350840A1 true ES350840A1 (en) 1969-12-01

Family

ID=8625936

Family Applications (1)

Application Number Title Priority Date Filing Date
ES350840A Expired ES350840A1 (en) 1967-02-24 1968-02-23 A prestressed concrete pressure vessel for nuclear reactors

Country Status (9)

Country Link
BE (1) BE710435A (en)
CH (1) CH489090A (en)
DE (1) DE1639163B1 (en)
ES (1) ES350840A1 (en)
FR (1) FR1538984A (en)
GB (1) GB1144840A (en)
LU (1) LU55449A1 (en)
NL (1) NL6802528A (en)
SE (1) SE329218B (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
SE435981B (en) * 1983-03-15 1984-10-29 Asea Atom Ab CONTAINING DEVICE CONTAINING A CONCRETE BODY WITH A ROTARY SHAFT MOVED, HEAD AS A ROTATION BODY DESIGNED OF A CONTAINING SPACE WITH AT LEAST ONE AXIAL DIRECTION WETTING OPENING, AND LOW

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1207427A (en) * 1958-03-03 1960-02-16 Sepi Improvements to vessels suitable for nuclear reactors
DE1093497B (en) * 1958-11-26 1960-11-24 Babcock & Wilcox Dampfkessel Reactor vessel
FR1332043A (en) * 1962-05-28 1963-12-16

Also Published As

Publication number Publication date
NL6802528A (en) 1968-08-26
CH489090A (en) 1970-04-15
LU55449A1 (en) 1968-04-23
DE1639163B1 (en) 1971-03-25
GB1144840A (en) 1969-03-12
SE329218B (en) 1970-10-05
FR1538984A (en) 1968-09-13
BE710435A (en) 1968-06-17

Similar Documents

Publication Publication Date Title
ES306050A1 (en) A nuclear reactor. (Machine-translation by Google Translate, not legally binding)
ES415537A1 (en) Transfer hood for handling fuel assemblies in nuclear reactors and especially fast reactors
ES355670A1 (en) Prestressed concrete pressure vessel for nuclear reactors
ES350840A1 (en) A prestressed concrete pressure vessel for nuclear reactors
GB789022A (en) Improvements in or relating to nuclear reactors
GB818667A (en) Improved construction of the cover of a heterogeneous nuclear reactor
GB962625A (en) Nuclear reactor
ES431106A1 (en) Fast reactor of the liquid sodium cooled type
GB1207217A (en) Prestressed concrete pressure vessel
GB1088787A (en) Heat extraction device for a reactor
GB983379A (en) Improvements in or relating to concrete pressure vessels
ES283111A1 (en) A method to eliminate heat and the products of fision and nuclear reactor of direct contact that makes it (Machine-translation by Google Translate, not legally binding)
GB1335528A (en) Pressure vessel
FR74657E (en) Deflector channels for nuclear reactor fuel rods
GB1075476A (en) Nuclear reactor and pressure vessel therefor
BE605951A (en) Process for preparing UO2 for fuel pellets intended for nuclear reactors
GB1246760A (en) Method of exchanging the moderator and fuel of a nuclear reactor, and reactor employing the method
GB1188905A (en) Nuclear Reactor Support Structure.
DK106980C (en) Method of inserting a temperature measuring means into the core of a fuel plate for nuclear reactor reactors.
GB1223638A (en) A demountable cover for a prestressed concrete vessel
GB1086056A (en) Improvements relating to core structures for gas-cooled nuclear reactors
GB1314498A (en) Nuclear reactors installtion
CH526836A (en) Fuel rod for gas-cooled high-temperature nuclear reactors and its use
GB822788A (en) Improvements in piles of moderator and/or reflector elements for nuclear reactors
ES282646A1 (en) Improvements in solid moderator combinations or couplings for nuclear reactor (Machine-translation by Google Translate, not legally binding)