GB976367A - Improvements in or relating to systems for detecting leaks in fuel elements in a nuclear reactor - Google Patents

Improvements in or relating to systems for detecting leaks in fuel elements in a nuclear reactor

Info

Publication number
GB976367A
GB976367A GB28073/62A GB2807362A GB976367A GB 976367 A GB976367 A GB 976367A GB 28073/62 A GB28073/62 A GB 28073/62A GB 2807362 A GB2807362 A GB 2807362A GB 976367 A GB976367 A GB 976367A
Authority
GB
United Kingdom
Prior art keywords
group
channels
monitoring system
reactor
channel
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
GB28073/62A
Inventor
Jane Cicely Thompson
Robert Vincent Ingham
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.)
THOMPSON NUCLEAR ENERGY CO Ltd
Nuclear Power Plant Co Ltd
Original Assignee
THOMPSON NUCLEAR ENERGY CO Ltd
Nuclear Power Plant Co Ltd
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 THOMPSON NUCLEAR ENERGY CO Ltd, Nuclear Power Plant Co Ltd filed Critical THOMPSON NUCLEAR ENERGY CO Ltd
Priority to GB28073/62A priority Critical patent/GB976367A/en
Publication of GB976367A publication Critical patent/GB976367A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/02Devices or arrangements for monitoring coolant or moderator
    • G21C17/04Detecting burst slugs
    • G21C17/041Detecting burst slugs characterised by systems for checking the coolant channels, e.g. matrix systems
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

976, 367. Monitoring reactors. NUCLEAR POWER PLANT CO. Ltd., and A. E. I.-JOHN THOMPSON NUCLEAR ENERGY CO. Ltd., [trading as NUCLEAR POWER GROUP]. April 29, 1963 [July 20, 1962], No. 28073/62. Heading G6C. In a leak detection system for fuel elements, at least two tapping points are provided per channel in at least some of the fuel channels of a nuclear reactor, and the two samples of cooling fluid taken from each such channel are conveyed to two independent fission product detection systems. In Fig. 1 the fuel channels 1 of a gas-cooled graphitemoderated reactor are connected in zones of 32 channels for the purpose of leak detection. Each zone is associated with a standpipe 2 and is divided into four groups a, b, c, and d. In each group samples of cooling gas from all the 8 channels are mixed together and pass to the outside of the reactor through group sample pipes 4. The sample taken from the other tapping point of each channel passes through a pipe 7 to a selector valve 8. In this way the group monitoring system and the individual channel monitoring system can operate independently of one another. Alternatively one tapping point may be connected to a group monitoring system and the other tapping point to a further group monitoring system for the same as a different group of channels. Specification 929,838 is referred to.
GB28073/62A 1962-07-20 1962-07-20 Improvements in or relating to systems for detecting leaks in fuel elements in a nuclear reactor Expired GB976367A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB28073/62A GB976367A (en) 1962-07-20 1962-07-20 Improvements in or relating to systems for detecting leaks in fuel elements in a nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB28073/62A GB976367A (en) 1962-07-20 1962-07-20 Improvements in or relating to systems for detecting leaks in fuel elements in a nuclear reactor

Publications (1)

Publication Number Publication Date
GB976367A true GB976367A (en) 1964-11-25

Family

ID=10269845

Family Applications (1)

Application Number Title Priority Date Filing Date
GB28073/62A Expired GB976367A (en) 1962-07-20 1962-07-20 Improvements in or relating to systems for detecting leaks in fuel elements in a nuclear reactor

Country Status (1)

Country Link
GB (1) GB976367A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2432750A1 (en) * 1978-08-03 1980-02-29 Gen Atomic Co LEAKAGE MONITORING DEVICE FOR A GAS COOLING FAST NEUTRON NUCLEAR REACTOR
FR2505079A1 (en) * 1981-04-30 1982-11-05 Novatome Ind COOLANT FLUID COLLECTION DEVICE FOR LOCATING DEFECTIVE COMBUSTIBLE ASSEMBLIES IN A NUCLEAR REACTOR IN SERVICE

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2432750A1 (en) * 1978-08-03 1980-02-29 Gen Atomic Co LEAKAGE MONITORING DEVICE FOR A GAS COOLING FAST NEUTRON NUCLEAR REACTOR
FR2505079A1 (en) * 1981-04-30 1982-11-05 Novatome Ind COOLANT FLUID COLLECTION DEVICE FOR LOCATING DEFECTIVE COMBUSTIBLE ASSEMBLIES IN A NUCLEAR REACTOR IN SERVICE
EP0064462A1 (en) * 1981-04-30 1982-11-10 Novatome Fast Nuclear Reactor comprising a core constituted by fuel assemblies and a device for locating defective fuel assemblies

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