GB987880A - A control rod drive for nuclear reactors - Google Patents

A control rod drive for nuclear reactors

Info

Publication number
GB987880A
GB987880A GB21463/61A GB2146361A GB987880A GB 987880 A GB987880 A GB 987880A GB 21463/61 A GB21463/61 A GB 21463/61A GB 2146361 A GB2146361 A GB 2146361A GB 987880 A GB987880 A GB 987880A
Authority
GB
United Kingdom
Prior art keywords
reactor
fluid
drive
drive system
moderator
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
GB21463/61A
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.)
Licentia Patent Verwaltungs GmbH
Original Assignee
Licentia Patent Verwaltungs GmbH
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
Priority claimed from DEL36378A external-priority patent/DE1230140B/en
Application filed by Licentia Patent Verwaltungs GmbH filed Critical Licentia Patent Verwaltungs GmbH
Publication of GB987880A publication Critical patent/GB987880A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control 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
    • G21C7/12—Means for moving control elements to desired position
    • G21C7/16—Hydraulic or pneumatic drive
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control 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
    • G21C7/12—Means for moving control elements to desired position
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control 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
    • G21C7/12—Means for moving control elements to desired position
    • G21C7/14—Mechanical drive 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
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structures Of Non-Positive Displacement Pumps (AREA)

Abstract

987, 880. Controlling nuclear reactors. LICENTIA PATENT-VERWALTUNGS G.m.b.H. June 14, 1961 [June 15, 1960], No. 21463/61. Drawings to Specification. Heading G6C. A control rod drive for a nuclear reactor comprises a mechanical drive system combined with a fluid drive system, the fluid of which is the same as that used as coolant and/or moderator in the core of the reactor, communication being provided between the pressure vessel of the reactor and the fluid drive system which is maintained at a pressure slightly below that in the pressure vessel so that during normal operation a portion of the reactor coolant and/or moderator will flow from the pressure vessel into the fluid drive system. The coolant and/or moderator fluid that emerges from the fluid drive system may be returned to the pressure vessel through a filter plant to remove corrosion products. The drive of the control rod for the control action may be effected by means of an electric motor, while the emergency or quick-acting shutting-down of the reactor is carried out by means of the above-mentioned fluid drive system, the fluid for which is stored under pressure in a separate supply reservoir. It is an advantage to combine the two drive systems so that one is disposed concentrically inside the other, thus reducing the overall structural height. As a result of the pressures within the control rod drive and the pressure vessel being nearly equal, special seals can be dispensed with and the drive has only to provide sufficient power to overcome the weight of the rod whereas in the devices hitherto known it was necessary to overcome both the internal pressure of the reactor and the friction at the seals. In addition, special lubrication of the drive is not required. The flow of hot coolant and/ or moderator uniformly heats the control drive in an advantageous manner, thermal stresses being avoided when the control rod is moved in and out of the reactor. In order to maintain the liquid which is under pressure in the supply reservoir for the emergency shut-down constantly at approximately the reactor operation temperature, a coil of pipe is arranged within the supply reservoir through which coil the hot coolant and/or moderator that emerges from the fluid drive system is caused to flow.
GB21463/61A 1960-06-15 1961-06-14 A control rod drive for nuclear reactors Expired GB987880A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DEL36378A DE1230140B (en) 1960-06-15 1960-06-15 Absorber rod drive for nuclear reactors

Publications (1)

Publication Number Publication Date
GB987880A true GB987880A (en) 1965-03-31

Family

ID=7267444

Family Applications (1)

Application Number Title Priority Date Filing Date
GB21463/61A Expired GB987880A (en) 1960-06-15 1961-06-14 A control rod drive for nuclear reactors

Country Status (1)

Country Link
GB (1) GB987880A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3632471A (en) * 1967-08-25 1972-01-04 Licentia Gmbh Rapid shutdown system for water-cooled nuclear reactors
US7197103B2 (en) 2001-12-13 2007-03-27 Framatome Anp Gmbh Control rod drive for a nuclear reactor and method for moving a control rod into a reactor core of a nuclear reactor

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3632471A (en) * 1967-08-25 1972-01-04 Licentia Gmbh Rapid shutdown system for water-cooled nuclear reactors
US7197103B2 (en) 2001-12-13 2007-03-27 Framatome Anp Gmbh Control rod drive for a nuclear reactor and method for moving a control rod into a reactor core of a nuclear reactor

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