DE2642156A1 - PROCEDURE AND EQUIPMENT FOR DETECTING DEFECTIVE FUEL RODS - Google Patents

PROCEDURE AND EQUIPMENT FOR DETECTING DEFECTIVE FUEL RODS

Info

Publication number
DE2642156A1
DE2642156A1 DE19762642156 DE2642156A DE2642156A1 DE 2642156 A1 DE2642156 A1 DE 2642156A1 DE 19762642156 DE19762642156 DE 19762642156 DE 2642156 A DE2642156 A DE 2642156A DE 2642156 A1 DE2642156 A1 DE 2642156A1
Authority
DE
Germany
Prior art keywords
water
cladding tube
procedure
fuel
fuel rods
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.)
Ceased
Application number
DE19762642156
Other languages
German (de)
Inventor
Heinz Dipl Ing Knaab
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.)
Kraftwerk Union AG
Original Assignee
Kraftwerk Union AG
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 Kraftwerk Union AG filed Critical Kraftwerk Union AG
Priority to DE19762642156 priority Critical patent/DE2642156A1/en
Priority to CH931777A priority patent/CH607802A5/en
Priority to FR7728225A priority patent/FR2365185A2/en
Priority to GB39006/77A priority patent/GB1531120A/en
Priority to JP11314777A priority patent/JPS5352895A/en
Publication of DE2642156A1 publication Critical patent/DE2642156A1/en
Ceased legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • G21C3/10End closures ; Means for tight mounting therefor
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/06Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • G21C17/07Leak testing
    • 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)

Description

KRAFTWERK UNION AKTIMGESSLLSCHAy1T Unssr Zeichen:KRAFTWERK UNION AKTIMGESSLLSCHAy 1 T Our sign:

VPA 78P 9 37 7 BRDVPA 78P 9 37 7 FRG

Verfahren und Einrichtung zur Auffindung defekter Brennstäbe (Zusatz zur Hauptanmeldung P 23 14 650.1-33 - VPA 65/1189)Process and device for finding defective fuel rods (addendum to main application P 23 14 650.1-33 - VPA 65/1189)

Die vorliegende Erfindung betrifft ein Verfahren zur Auffindung eines defekten Hüllrohres eines Brennstabes im Verband kompletter Brennelemente wassergekühlter Kernreaktoren nach der Hauptanmeldung P 23 14 650.1-33 - VPA 65/1189, wonach das Hüllrohr in der Nähe einer zugänglichen Endkappe erwärmt wird und evtl. im Inneren des Hüllrohres befindliches Wasser durch Messung des zeitlichen Temperaturverlaufes bzw. mit Hilfe des Ultraschall-Impuls-Echo-Verfahrens ermittelt wird. Die Durchführung dieses Verfahrens in der Praxis hat gezeigt, daß Grenzfälle vorkommen können, bei denen dieses Verfahren keine Anzeige erbringt, obwohl der Brennstab undicht ist. Solche Grenzfälle treten auf, wenn der Defekt des Hüllrohres sehr klein ist und der Zeitpunkt seines Eintretens so kurz vor der überprüfung liegt, daß praktisch noch kein Wasser in das Innere des Brennstabes eintreten konnte.The present invention relates to a method for finding a defective cladding tube of a fuel rod in a complete assembly Fuel elements of water-cooled nuclear reactors according to the main application P 23 14 650.1-33 - VPA 65/1189, according to which the cladding tube in near an accessible end cap and possibly water inside the cladding tube by measuring the temporal temperature profile or with the help of the ultrasonic pulse-echo method is determined. The implementation of this procedure in practice has shown that borderline cases occur where this method does not produce an indication even though the fuel rod is leaking. Such borderline cases occur when the defect of the cladding tube is very small and the time of its occurrence is so close to the check that practically still no water could enter the inside of the fuel rod.

Es stellte sich daher die Aufgabe, das in der Hauptanmeldung beschriebene Verfahren so zu verbessern, daß auch noch derartige Grenzfälle erfaßt werden können, d.h. daß eine möglichst 100#ige Anzeigesicherheit erreicht werden kann.The task therefore arose, that described in the main application To improve the process in such a way that such borderline cases can also be covered, i.e. that a 100 # Display security can be achieved.

Diese Aufgabe wird erfindungsgemäß dadurch gelöst, daß die Brennelemente, vorzugsweise vor Beginn des Meßverfahrens,einer an sich bekannten hydrostatischen Druckwechselbehandlung unterworfenThis object is achieved in that the Fuel elements, preferably before the start of the measurement process, one on subjected to known hydrostatic pressure change treatment

809812/0330
Mü 21 Ant / 23.8.1976
809812/0330
Mü 21 Ant / 23.8.1976

Solche DruckwechselbeharMVlungen sind an sich bekannt, siehe die deutsche Auslegeschrift 1 248 822. Diese Behandlung hatte dort die Aufgabe, den Austritt radioaktiver Spaltprodukte in das Wasser des Prüfbehälters zu verstärken bzw. zu beschleunigen und dadurch das Prüfverfahren, bei dem dann die Radioaktivität des das Brennelement in der Prüfkammer umgebenden Wassers gemessen werden sollte, zu verbessern. Im vorliegenden Fall dient die Anwendung einer Druckwechselbeanspruchung dazu, das Eindringen des Wassers durch ein kleines Leck im Hüllrohr zu beschleunigen bzw. erst zu bewirken, so daß damit das in der Hauptanmeldung beschriebene Verfahren mit Sicherheit auch die eingangs genannten Grenzfälle zu erfassen gestattet. Such DruckwechselbeharMVlungen are known per se, see the German Auslegeschrift 1 248 822. This treatment had the task of preventing radioactive fission products from escaping into the To strengthen or accelerate the water of the test container and thereby the test method, in which then the radioactivity of the water surrounding the fuel assembly in the test chamber should be measured. In the present case serves the use of alternating pressure stress to accelerate the penetration of water through a small leak in the cladding tube or to be effected first, so that the method described in the main application also allows the borderline cases mentioned at the outset to be covered with certainty.

Die Druckwechselbeanspruchung kann dabei, ähnlich wie in der genannten Auslegeschrift 1 248 822, in einem gesonderten Behälter stattfinden. Als Druckwechsel kommen sowohl Verminderungen als auch Erhöhungen des Druckes gegenüber dem Ausgangsniveau infrage.The alternating pressure stress can, similar to that in Auslegeschrift 1 248 822 mentioned above, take place in a separate container. There are both reductions in pressure changes as well as increases in pressure compared to the initial level.

Eine Beschädigung intakter Brennstäbe ist dabei nicht zu befürchten, im ungünstigsten Fall werden dadurch höchstens kurz vor einem Defekt stehende Brennstäbe leckgeschlagen. Dies ist jedoch kein Fehler, sondern erhöht vielmehr die Sicherheit des nachfolgenden Reaktorbetriebes, da damit auch vermieden wird, daß kurz vor einem Defekt stehende Brennstäbe für die Wiederbeladung des Reaktorkernes weiter verwendet werden.There is no risk of damage to intact fuel rods, In the worst case scenario, fuel rods that are just about to become defective will leak. However, this is not a mistake, but rather increases the safety of the following Reactor operation, since this also prevents fuel rods that are about to malfunction for reloading of the reactor core can still be used.

Eine weitere Erhöhung der Ansprechempfindlichkeit des im Hauptpatent beschriebenen Verfahrens wird durch eine aus den Fig.A further increase in the sensitivity of the main patent The method described is carried out by one of FIGS.

und 2 ersichtliche Gestaltung der inneren Endkappenoberfläche 24a, 24b erreicht. Diese Figuren entsprechend im Übrigen der Fig. des Hauptpatentes einschließlich der Bezugszeichen. Durch diese kegelige Gestaltung wird zunächst die der Kondensation dienende Oberfläche vergrößert und Bildung sowie Ablauf der Tropfen 26 erleichtert. Auf diese Weise gelingt es bereits, geringe Feuchtig-and FIG. 2 shows the design of the inner end cap surface 24a, 24b reached. These figures otherwise correspond to the figures of the main patent including the reference numerals. Through this conical design, the surface used for condensation is first enlarged and the droplets 26 are formed and run off relieved. In this way, it is already possible to remove small amounts of moisture

809812/0330809812/0330

keitsmengen durch Kondensation zu erfassen und damit zur Anzeige zu "bringen.to capture the amount of time due to condensation and thus to To bring display.

2 Patentansprüche 2 Figuren2 claims 2 figures

809812/0330809812/0330

Claims (2)

·<* ' 76P 937 7 BRD· <* '76P 937 7 FRG Patentansprüche _ ". ^1 Eß Claims _ ". ^ 1 Eß Verfahren zur Auffindung eines defekten Hüllrohres eines 'Brennstabes im Verband kompletter Brennelemente wassergekühlter Kernreaktoren nach Hauptanmeldung P 23 14 650.1-33 VPA 65/1189, wonach das Hüllrohr in der Nähe einer zugänglichen Endkappe erwärmt wird und evtl. im Inneren des Hüllrohres befindliches Wasser durch Messung des zeitlichen Temperaturverlaufes bzw. mit Hilfe des Ultraschallimpuls-Echo-Verfahrens ermittelt wird, dadurch gekennzeichnet, daß die Brennelemente, vorzugsweise vor Beginn dieses Verfahrens, einer an sich bekannten Druckwechselbehandlung unter Wasser unterworfen werden.Method for finding a defective cladding tube of a 'fuel rod in the assembly of complete fuel elements of water-cooled nuclear reactors according to main application P 23 14 650.1-33 VPA 65/1189, after which the cladding tube is heated in the vicinity of an accessible end cap and any water located inside the cladding tube by measuring the time Temperature profile or is determined with the aid of the ultrasonic pulse-echo method, characterized in that the fuel assemblies, preferably before the start of this procedure, be subjected to a pressure change treatment known per se under water. 2. Einrichtung zur erleichterten Durchführung des Verfahrens nach Anspruch 1, dadurch gekennzeichnet, daß die innere dem Kernbrennstoff zugewandte Seite der Endkappen (24) durch eine im allgemeinen kegelige Gestaltung (24a/24b) vergrößert und zur raschen Ablösung von Kondenswassertropfen (26) mit einem zentralen Vorsprung versehen ist.2. Facility to facilitate the implementation of the procedure according to claim 1, characterized in that the inner side of the end caps (24) facing the nuclear fuel by a generally conical design (24a / 24b) is enlarged and provided with a central projection for the rapid removal of drops of condensation water (26). .809812/0330.809812 / 0330 ORIGfNALlNSPECTEDORIGfNALlNSPECTED
DE19762642156 1973-03-23 1976-09-20 PROCEDURE AND EQUIPMENT FOR DETECTING DEFECTIVE FUEL RODS Ceased DE2642156A1 (en)

Priority Applications (5)

Application Number Priority Date Filing Date Title
DE19762642156 DE2642156A1 (en) 1976-09-20 1976-09-20 PROCEDURE AND EQUIPMENT FOR DETECTING DEFECTIVE FUEL RODS
CH931777A CH607802A5 (en) 1976-09-20 1977-07-28 Method for detecting defective fuel rods
FR7728225A FR2365185A2 (en) 1973-03-23 1977-09-19 Defective fuel element can identified by contained water - after pressurising to increase water leakage and sensitivity of test
GB39006/77A GB1531120A (en) 1976-09-20 1977-09-19 Testing nuclear fuel rods
JP11314777A JPS5352895A (en) 1976-09-20 1977-09-20 Method and device for detecting broken fuel rod

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19762642156 DE2642156A1 (en) 1976-09-20 1976-09-20 PROCEDURE AND EQUIPMENT FOR DETECTING DEFECTIVE FUEL RODS

Publications (1)

Publication Number Publication Date
DE2642156A1 true DE2642156A1 (en) 1978-03-23

Family

ID=5988316

Family Applications (1)

Application Number Title Priority Date Filing Date
DE19762642156 Ceased DE2642156A1 (en) 1973-03-23 1976-09-20 PROCEDURE AND EQUIPMENT FOR DETECTING DEFECTIVE FUEL RODS

Country Status (4)

Country Link
JP (1) JPS5352895A (en)
CH (1) CH607802A5 (en)
DE (1) DE2642156A1 (en)
GB (1) GB1531120A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4366711A (en) * 1979-04-20 1983-01-04 Framatome Method of testing fuel rods for assemblies for nuclear reactors and corresponding apparatus
US4410484A (en) * 1979-09-26 1983-10-18 Framatome Process and apparatus for acoustic and ultrasonic detection of defective nuclear reactor fuel assemblies

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4366711A (en) * 1979-04-20 1983-01-04 Framatome Method of testing fuel rods for assemblies for nuclear reactors and corresponding apparatus
US4410484A (en) * 1979-09-26 1983-10-18 Framatome Process and apparatus for acoustic and ultrasonic detection of defective nuclear reactor fuel assemblies

Also Published As

Publication number Publication date
JPS5352895A (en) 1978-05-13
GB1531120A (en) 1978-11-01
CH607802A5 (en) 1978-10-31

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