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1. WO2016096499 - DEVICE AND METHOD FOR PERFORMING A LEAK TEST ON FUEL ROD CAPSULES

Publication Number WO/2016/096499
Publication Date 23.06.2016
International Application No. PCT/EP2015/078808
International Filing Date 07.12.2015
IPC
G01M 3/20 2006.1
GPHYSICS
01MEASURING; TESTING
MTESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
3Investigating fluid tightness of structures
02by using fluid or vacuum
04by detecting the presence of fluid at the leakage point
20using special tracer materials, e.g. dye, fluorescent material, radioactive material
G21C 17/07 2006.1
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
17Monitoring; Testing
06Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
07Leak testing
G21C 19/07 2006.1
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
19Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
02Details of handling arrangements
06Means for supporting or storing fuel elements or control elements
07Storage racks; Storage pools
CPC
G01M 3/205
GPHYSICS
01MEASURING; TESTING
MTESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
3Investigating fluid-tightness of structures
02by using fluid or vacuum
04by detecting the presence of fluid at the leakage point
20using special tracer materials, e.g. dye, fluorescent material, radioactive material
202using mass spectrometer detection systems
205Accessories or associated equipment; Pump constructions
G21C 17/07
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
17Monitoring; Testing
06Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
07Leak testing
G21C 19/07
GPHYSICS
21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
CNUCLEAR REACTORS
19Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
02Details of handling arrangements
06Magazines for holding fuel elements or control elements
07Storage racks; Storage pools
Y02E 30/30
YSECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
30Energy generation of nuclear origin
30Nuclear fission reactors
Applicants
  • AREVA GMBH [DE]/[DE]
Inventors
  • HUMMEL, Wolfgang
Agents
  • SCHLÖGL, Markus
Priority Data
102014118623.015.12.2014DE
Publication Language German (de)
Filing Language German (DE)
Designated States
Title
(DE) VORRICHTUNG UND VERFAHREN ZUR DURCHFÜHRUNG EINER DICHTHEITSPRÜFUNG AN BRENNSTABKAPSELN
(EN) DEVICE AND METHOD FOR PERFORMING A LEAK TEST ON FUEL ROD CAPSULES
(FR) DISPOSITIF ET PROCÉDÉ POUR RÉALISER UN TEST D'ÉTANCHÉITÉ DE CAPSULES DE BARRES DE COMBUSTIBLE
Abstract
(DE) Eine Vorrichtung(1) zur Durchführung einer Dichtheitsprüfung an einer zumindest einen Brennstab(2) und Prüfgas(P) enthaltenden Brennstabkapsel(3) umfasst ein zur Aufnahme zumindest einer Brennstabkapsel(3) ausgebildetes Testbehältnis(4), welches in ein mit Wasser geflutetem Becken(5) einer nukleartechnischen Anlage absenkbar ist. Erfindungsgemäß ist ein Massenspektrometer(14) mit einem Inneren des Testbehältnisses(4) derart fluidtechnisch verbindbar, dass dem Massenspektrometers(14) ein Gasstrom zur Erfassung einer Konzentration des aus der Brennstabkapsel(3) in das Testbehältnis(4) diffundierten Prüfgases(P) zuführbar ist.
(EN) The invention relates to a device (1) for performing a leak test on a fuel rod capsule (3), which contains at least one fuel rod (2) and test gas (P), which device (1) comprises a test container (4), which is designed to accommodate at least one fuel rod capsule (3) and can be lowered into a pool (5) of a nuclear plant flooded with water. According to the invention, a mass spectrometer (14) is fluidically connected to the interior of the test container (4) in such a way that a gas flow can be fed to the mass spectrometer (14) in order to sense the concentration of the test gas (P) that has diffused into the test container (4) from the fuel rod capsule (3).
(FR) L'invention concerne un dispositif (1) destiné à effectuer un test d'étanchéité au niveau d'une capsule de barres de combustible (3) contenant au moins une barre de combustible (2) et un gaz de test (P), lequel dispositif comprend un récipient de test (4) qui est adapté pour recevoir au moins une capsule de barres de combustible (3) et qui peut être abaissé dans un bassin (5) rempli d'eau d'une centrale nucléaire. Selon l'invention, un spectromètre de masse (14) peut être relié par une technique fluidique à l'intérieur du récipient de test (4) de sorte qu'un flux de gaz, destiné à détecter une concentration du gaz de test (P) diffusé de la capsule de barres de combustible (3) dans le récipient de test (4), peut être amené au spectromètre de masse (14).
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