JPS6429797A - Control rod assembly - Google Patents

Control rod assembly

Info

Publication number
JPS6429797A
JPS6429797A JP62184824A JP18482487A JPS6429797A JP S6429797 A JPS6429797 A JP S6429797A JP 62184824 A JP62184824 A JP 62184824A JP 18482487 A JP18482487 A JP 18482487A JP S6429797 A JPS6429797 A JP S6429797A
Authority
JP
Japan
Prior art keywords
pellets
cladding pipe
spacing
liquid metal
metallic body
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.)
Granted
Application number
JP62184824A
Other languages
Japanese (ja)
Other versions
JPH0584876B2 (en
Inventor
Toshikatsu Yamanaka
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP62184824A priority Critical patent/JPS6429797A/en
Publication of JPS6429797A publication Critical patent/JPS6429797A/en
Publication of JPH0584876B2 publication Critical patent/JPH0584876B2/ja
Granted legal-status Critical Current

Links

Classifications

    • 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

  • Particle Accelerators (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To expand the spacing between a cladding pipe and pellets and to extend the life thereof accordingly by disposing at least either of an elastic metallic body and liquid metal between the cladding pipe of a control rod element and the pellets. CONSTITUTION:The elastic metallic body 107 is mounted into the annular spacing 111 between the pellets 104 and the cladding pipe 101. This elastic metallic body 107 is made of an austenitic stainless steel and has a fiber mesh form. The pellets 104 are thereby supported in the central position in the cladding pipe 101 and the fluctuation in the distribution of generated heat and the distribution of neutron absorption is eliminated; in addition, the fall of the splinters of the pellets is prevented in the event of the rupture of the pellets. The liquid metal sodium 108 is packed into the cladding pipe 101 up to a liquid level 109 in the upper part of the pellets 104. Gaseous He released from the pellets 104 by irradiation is pushed into an upper plenum 110 by the difference in density between said gas and the liquid metal sodium 108. The liquid metal sodium 108 is, therefore, interposed into the spacing 111 and the heat transfer performance is improved by the high thermal conductivity thereof, regardless of the expansion of the spacing 111.
JP62184824A 1987-07-24 1987-07-24 Control rod assembly Granted JPS6429797A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP62184824A JPS6429797A (en) 1987-07-24 1987-07-24 Control rod assembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP62184824A JPS6429797A (en) 1987-07-24 1987-07-24 Control rod assembly

Publications (2)

Publication Number Publication Date
JPS6429797A true JPS6429797A (en) 1989-01-31
JPH0584876B2 JPH0584876B2 (en) 1993-12-03

Family

ID=16159936

Family Applications (1)

Application Number Title Priority Date Filing Date
JP62184824A Granted JPS6429797A (en) 1987-07-24 1987-07-24 Control rod assembly

Country Status (1)

Country Link
JP (1) JPS6429797A (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2772509A1 (en) * 1997-12-11 1999-06-18 Japan Nuclear Cycle Dev Inst Neutron absorption pin has a thermal expansion-matched sheathed absorber
FR2776116A1 (en) * 1998-03-11 1999-09-17 Wolfgang Schulz CONTROL ELEMENT FOR A NUCLEAR REACTOR
US6246740B1 (en) * 1997-10-14 2001-06-12 Japan Nuclear Cycle Development Institute SIC-composite material sleeve and process for producing the same
JP2009098063A (en) * 2007-10-18 2009-05-07 Hitachi-Ge Nuclear Energy Ltd Bellows and universal bellows using thte same, piping system for fast breeder reactor, and fast breeder reactor facility
WO2012094152A1 (en) 2011-01-06 2012-07-12 Westinghouse Electric Company Llc Nuclear fuel rod plenum spring assembly

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS497834A (en) * 1972-05-12 1974-01-24
JPS5279197A (en) * 1975-12-26 1977-07-04 Hitachi Ltd Nuclear fuel element
JPS5798893A (en) * 1980-12-12 1982-06-19 Nippon Atomic Ind Group Co Nuclear reactor control rod

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS497834A (en) * 1972-05-12 1974-01-24
JPS5279197A (en) * 1975-12-26 1977-07-04 Hitachi Ltd Nuclear fuel element
JPS5798893A (en) * 1980-12-12 1982-06-19 Nippon Atomic Ind Group Co Nuclear reactor control rod

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US6246740B1 (en) * 1997-10-14 2001-06-12 Japan Nuclear Cycle Development Institute SIC-composite material sleeve and process for producing the same
FR2772509A1 (en) * 1997-12-11 1999-06-18 Japan Nuclear Cycle Dev Inst Neutron absorption pin has a thermal expansion-matched sheathed absorber
FR2776116A1 (en) * 1998-03-11 1999-09-17 Wolfgang Schulz CONTROL ELEMENT FOR A NUCLEAR REACTOR
JP2009098063A (en) * 2007-10-18 2009-05-07 Hitachi-Ge Nuclear Energy Ltd Bellows and universal bellows using thte same, piping system for fast breeder reactor, and fast breeder reactor facility
WO2012094152A1 (en) 2011-01-06 2012-07-12 Westinghouse Electric Company Llc Nuclear fuel rod plenum spring assembly
JP2014506330A (en) * 2011-01-06 2014-03-13 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー Nuclear fuel rod plenum spring assembly
EP2661751A4 (en) * 2011-01-06 2017-10-04 Westinghouse Electric Company LLC Nuclear fuel rod plenum spring assembly

Also Published As

Publication number Publication date
JPH0584876B2 (en) 1993-12-03

Similar Documents

Publication Publication Date Title
ES8601547A1 (en) Guide tubes for light water nuclear reactor fuel assemblies.
FR2389970A1 (en)
ES8506932A1 (en) Neutron absorber pellets with modified microstructure
JPS6429797A (en) Control rod assembly
ES8703040A1 (en) A nuclear reactor control rod having a reduced worth tip.
GB921281A (en) Concentric tube structure
US3284315A (en) Nuclear reactor fuel element assembly
ES8702030A1 (en) Annular fuel rods for nuclear reactors.
JPS5445493A (en) Nuclear fuel element
GB940856A (en) Improvements in fuel elements for use in nuclear reactors
GB1498368A (en) Nuclear fuel element
US4587091A (en) Nuclear fuel assembly
EP0094732A3 (en) Improved steam generator for liquid metal fast breeder reactor
KR940003796B1 (en) Nucear reactor
JPS5481490A (en) Reactor fuel rods
JPS6473297A (en) Reactor instrumentation pipe
RU95113294A (en) NUCLEAR REACTOR CONTROL ROD
FR2409578A1 (en) MODERATE GRAPHITE NUCLEAR REACTOR COOLED BY GAS
JPS6473290A (en) Liquid metal fast furnace
FR2346814A1 (en) Inverted 'top hat' support for upper reactor components - e.g. for control rod operating elements in a reactor pressure vessel
GB818779A (en) Improvements in or relating to nuclear reactors
RU96115539A (en) NUCLEAR REACTOR CONTROL ROD
Deitrich et al. Summary and evaluation of fuel dynamics transient-overpower experiments: status 1974
Tillack et al. The Prometheus IFE reactor cavity
JPS54118980A (en) Nuclear fuel element