FR2077503A7 - Forced circulation liquid cooled nuclear - reactor - Google Patents

Forced circulation liquid cooled nuclear - reactor

Info

Publication number
FR2077503A7
FR2077503A7 FR7034882A FR7034882A FR2077503A7 FR 2077503 A7 FR2077503 A7 FR 2077503A7 FR 7034882 A FR7034882 A FR 7034882A FR 7034882 A FR7034882 A FR 7034882A FR 2077503 A7 FR2077503 A7 FR 2077503A7
Authority
FR
France
Prior art keywords
pipe
reactor
forced circulation
liquid cooled
circulation liquid
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
FR7034882A
Other languages
French (fr)
Other versions
FR2077503B3 (en
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.)
Studsvik Energiteknik AB
Original Assignee
Studsvik Energiteknik AB
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 Studsvik Energiteknik AB filed Critical Studsvik Energiteknik AB
Application granted granted Critical
Publication of FR2077503A7 publication Critical patent/FR2077503A7/en
Publication of FR2077503B3 publication Critical patent/FR2077503B3/fr
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/12Means for moving control elements to desired position
    • G21C7/16Hydraulic or pneumatic drive
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/326Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

Each fuel element is extended upwards from the core into an integral or two section spigot jointed pipe through which the coolant is ejected from below. A float of neutron absorbent material in this pipe takes up a position dependent on the pressure drop produced by the coolant flow. Gated flow control outlets may be provided at the centre of the pipe above the core to set the float height and at the top of the pipe and there may be a gated inlet at the bottom.
FR7034882A 1969-09-26 1970-09-25 Forced circulation liquid cooled nuclear - reactor Expired FR2077503A7 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
SE13279/69A SE332033B (en) 1969-09-26 1969-09-26

Publications (2)

Publication Number Publication Date
FR2077503A7 true FR2077503A7 (en) 1971-10-29
FR2077503B3 FR2077503B3 (en) 1973-06-29

Family

ID=20297150

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7034882A Expired FR2077503A7 (en) 1969-09-26 1970-09-25 Forced circulation liquid cooled nuclear - reactor

Country Status (3)

Country Link
DE (1) DE2047253A1 (en)
FR (1) FR2077503A7 (en)
SE (1) SE332033B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0031541A2 (en) * 1979-12-28 1981-07-08 Ab Asea-Atom Boiling-water nuclear reactor
FR2576135A1 (en) * 1985-01-16 1986-07-18 Kraftwerk Union Ag Control rod hydraulic drive esp. using primary coolant

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6804320B2 (en) 2002-04-12 2004-10-12 Bechtel Bwxt Idaho, Llc Automatically scramming nuclear reactor system

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0031541A2 (en) * 1979-12-28 1981-07-08 Ab Asea-Atom Boiling-water nuclear reactor
EP0031541A3 (en) * 1979-12-28 1981-07-22 Ab Asea-Atom Boiling-water nuclear reactor
FR2576135A1 (en) * 1985-01-16 1986-07-18 Kraftwerk Union Ag Control rod hydraulic drive esp. using primary coolant

Also Published As

Publication number Publication date
SE332033B (en) 1971-01-25
FR2077503B3 (en) 1973-06-29
DE2047253A1 (en) 1971-06-03

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Legal Events

Date Code Title Description
ST Notification of lapse