Published August 2, 1977 | Version v1
Patent Open

Detection of fuel rod leakage

Description

Nuclear reactor fuel rod leakage is determined by measurement of vibrational characteristics of a resilient, flexible means sealed within the upper end caps of the fuel elements. The flexible means, which is preferably a metallic diaphragm, is set into motion by the impact of an internal metal rod which is operated by an external magnetic field, thereby permitting an indication of the pressure inside a fuel element without disturbing the welded assembly. The metal rod is activated and the vibration measurements are made through the use of a special tool which fits near the end cap of the fuel element to be tested. 5 claims, 8 figures

Files

9365838.pdf

Files (409.5 kB)

Name Size Download all
md5:09c207f28e380b1e3b9c1e34e42ce87c
409.5 kB Preview Download

Additional details

Publishing Information

Imprint Pagination
8 p.
IPC:
Int. Cl.G21C17/00.
IPC
Int. Cl.G21C17/00.
Patent number
US patent document 4,039,375/A/

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
9365838
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
FAILED ELEMENT DETECTION; FAILED ELEMENT MONITORS; FUEL ELEMENTS; SPECIFICATIONS
Descriptors DEC
REACTOR COMPONENTS