GB914380A - Improvements in or relating to nuclear reactors - Google Patents

Improvements in or relating to nuclear reactors

Info

Publication number
GB914380A
GB914380A GB2684/61A GB268461A GB914380A GB 914380 A GB914380 A GB 914380A GB 2684/61 A GB2684/61 A GB 2684/61A GB 268461 A GB268461 A GB 268461A GB 914380 A GB914380 A GB 914380A
Authority
GB
United Kingdom
Prior art keywords
channel
thermocouple
stem
junction
wall
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
GB2684/61A
Inventor
Roddie Mckeague
Thomas Anderson
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB2684/61A priority Critical patent/GB914380A/en
Publication of GB914380A publication Critical patent/GB914380A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/10Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/112Measuring temperature
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

914,380. Nuclear reactors. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. Oct. 19, 1961 [Jan. 23, 1961], No. 2684/61. Class 39 (4). Temperature measurement means for a fuel element channel of a nuclear reactor comprises a thermocouple stem adapted to be disposed within the channel, to extend outwardly from the fuel element intended to be nearest the reactor charge face when the fuel elements are in operative position within the channel, and to support a thermocouple hot junction for exposure to coolant in the channel. In Fig. 1 the thermocouple stem comprises an outer tubular member 3 and a telescoping inner tubular member 4, the outer member being supported by radial lugs 6 from a lip 5 in the fuel channel and the inner member terminating in a cone adapted for stacking arrangement with a cup at the upper end of the uppermost fuel element (not shown). The hot junction 7 of a thermocouple is clipped to the exterior surface of the wall of member 3 and is connected by a lead 8 to a remote indicator instrument outside the reactor core. In an alternative, Fig. 2 (not shown), the junction 7 projects radially outward from the wall of member 3 to make direct contact with the coolant gas. In a modification, Fig. 3 (not shown), the junction 7 is surrounded by an open-ended shield which screens it against heat radiated from the channel wall and provides some protection against damage during charging operations. In a further arrangement, Fig. 4 (not shown), apertures are provided in members 3 and 4 to allow coolant to flow inside the thermocouple stem, and the hot junction 7 is located inside the stem. Specification 907,735 is referred to.
GB2684/61A 1961-01-23 1961-01-23 Improvements in or relating to nuclear reactors Expired GB914380A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB2684/61A GB914380A (en) 1961-01-23 1961-01-23 Improvements in or relating to nuclear reactors

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB2684/61A GB914380A (en) 1961-01-23 1961-01-23 Improvements in or relating to nuclear reactors

Publications (1)

Publication Number Publication Date
GB914380A true GB914380A (en) 1963-01-02

Family

ID=9743964

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2684/61A Expired GB914380A (en) 1961-01-23 1961-01-23 Improvements in or relating to nuclear reactors

Country Status (1)

Country Link
GB (1) GB914380A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3945245A (en) * 1973-03-23 1976-03-23 Siemens Aktiengesellschaft Method and equipment for detecting deflective nuclear fuel rods

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3945245A (en) * 1973-03-23 1976-03-23 Siemens Aktiengesellschaft Method and equipment for detecting deflective nuclear fuel rods

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