GB1533789A - Method of and apparatus for the early malfunction detection in nuclear reactors - Google Patents

Method of and apparatus for the early malfunction detection in nuclear reactors

Info

Publication number
GB1533789A
GB1533789A GB18966/76A GB1896676A GB1533789A GB 1533789 A GB1533789 A GB 1533789A GB 18966/76 A GB18966/76 A GB 18966/76A GB 1896676 A GB1896676 A GB 1896676A GB 1533789 A GB1533789 A GB 1533789A
Authority
GB
United Kingdom
Prior art keywords
coolant
nuclear reactors
time constant
malfunction detection
fluctuations
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
GB18966/76A
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.)
European Atomic Energy Community Euratom
Original Assignee
European Atomic Energy Community Euratom
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 European Atomic Energy Community Euratom filed Critical European Atomic Energy Community Euratom
Publication of GB1533789A publication Critical patent/GB1533789A/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
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

1533789 Fault finding in coolant systems EUROPEAN ATOMIC ENERGY COMMUNITY 7 May 1976 [7 May 1975] 18966/76 Heading G1N Temperature fluctuations in the coolant for a nuclear reactor are measured by a sensor 4 Fig. 1 located downstream of a bundle of rods 1, consisting of two thermocouples in series opposition, one with a short time constant and the other with a long time constant. The fluctuations T are analyzed to determine where p(T) is the probability density function, and γ in S is the root mean square value of T. The value and the sign of the factor S is said to be indicative of the size and position of a blockage 5 in the coolant channel 2.
GB18966/76A 1975-05-07 1976-05-07 Method of and apparatus for the early malfunction detection in nuclear reactors Expired GB1533789A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
LU72426A LU72426A1 (en) 1975-05-07 1975-05-07

Publications (1)

Publication Number Publication Date
GB1533789A true GB1533789A (en) 1978-11-29

Family

ID=19727927

Family Applications (1)

Application Number Title Priority Date Filing Date
GB18966/76A Expired GB1533789A (en) 1975-05-07 1976-05-07 Method of and apparatus for the early malfunction detection in nuclear reactors

Country Status (4)

Country Link
DE (1) DE2620054A1 (en)
FR (1) FR2310613A1 (en)
GB (1) GB1533789A (en)
LU (1) LU72426A1 (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5088629A (en) * 1990-07-30 1992-02-18 Neill Richard K O Pressure build-up pump sprayer having improved valving means

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1252257A (en) * 1967-12-28 1971-11-03
DE1917590A1 (en) * 1969-04-05 1970-10-15 Interatom Fuel element hot spot detectors for sodium - cooled reactors
FR2176522A1 (en) * 1972-03-22 1973-11-02 Commissariat Energie Atomique Thermoelectric thermometry system - for liquid metal nuclear reactor coolant

Also Published As

Publication number Publication date
FR2310613A1 (en) 1976-12-03
LU72426A1 (en) 1977-02-09
DE2620054A1 (en) 1976-11-18
FR2310613B1 (en) 1980-06-06

Similar Documents

Publication Publication Date Title
GB1240235A (en) Method for the non-destructive assay of bulk nuclear reactor fuel and apparatus
GB1168198A (en) Detection, Identification and Analysis of Fissionable Isotopes
GB1345272A (en) Instrumentation for nuclear reactor
GB1061535A (en) Improvements in method and apparatus for measuring radiation
ES465869A1 (en) Instrumentation assembly for nuclear reactor
Gandini et al. New developments in generalized perturbation methods in the nuclide field
GB1533789A (en) Method of and apparatus for the early malfunction detection in nuclear reactors
US2931761A (en) Neutronic reactor control
GB1002880A (en) Boron-12 beta decay neutron detector
GB1470123A (en) Method of obtaining an indication of the identity of a leaking fuel element in a fast breeder power reactor
GB1115850A (en) Improvements in and relating to the measurement of the density of the fluid coolant from a nuclear reactor
GB1170030A (en) Device for measuring the Deposition of Solids from Coolants in Nuclear Reactors
EP0042099A3 (en) Self-regulating neutron coincidence counter
JPS5267686A (en) Device for measuring spacial distribution of neutrons
JPS52139897A (en) Measuring method and device for core coolant flow quantity in reactor
Kimel et al. Determination of Time Behavior of neutron Density and of Reactivity on the Argonaut Reactor
Carroll et al. The Effect of Fission Density on Fission-Gas Release
Csongor Atmospheric85Kr measurements between 1966 and 1968 in Debrecen (Hungary)
Sontheimer et al. RELEASE OF THc VOLATILE FISSION PRODUCTS Xe, Kr AND Cs FROM PWR FUEL UNDER STEADY AND TRANSIENT CONDITIONS UP TO HIGH BURNUP
JPS54159587A (en) Abnormality detector of neutron flux measuring apparatus for nuclear reactor
JPS5316193A (en) Failed fuel in core detecting method
Lee et al. CALCULATION OF DELAYED NEUTRON MULTIPLICATION IN THIN SUBCRITICAL SYSTEMS
Yasuda et al. Application of polarity correlation method to graphite moderated reactor
Wang et al. Subcritical reactivity as determined from reactor noise
JPS53107594A (en) Rector neutron flux detector

Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee