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Title: Method and apparatus for diagnosing breached fuel elements

Abstract

The invention provides an apparatus and method for diagnosing breached fuel elements in a nuclear reactor. A detection system measures the activity of isotopes from the cover gas in the reactor. A data acquisition and processing system monitors the detection system and corrects for the effects of the cover-gas clean up system on the measured activity and further calculates the derivative curve of the corrected activity as a function of time. A plotting system graphs the derivative curve, which represents the instantaneous release rate of fission gas from a breached fuel element. 8 figs.

Inventors:
; ;
Issue Date:
Research Org.:
Argonne National Lab., IL (USA)
OSTI Identifier:
6823763
Patent Number(s):
-US-A6020997
Assignee:
ANL; ERA-14-000616; EDB-88-183589
DOE Contract Number:  
W-31109-ENG-38
Resource Type:
Patent
Resource Relation:
Other Information: Portions of this document are illegible in microfiche products
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; FAILED ELEMENT MONITORS; DESIGN; ACTIVITY LEVELS; DATA ACQUISITION SYSTEMS; DETECTION; FAILED ELEMENT DETECTION; FUEL ELEMENT FAILURE; HOT GAS CLEANUP; INVENTIONS; ACCIDENTS; MEASURING INSTRUMENTS; MONITORS; PURIFICATION; REACTOR ACCIDENTS 220300* -- Nuclear Reactor Technology-- Fuel Elements; 220400 -- Nuclear Reactor Technology-- Control Systems

Citation Formats

Gross, K.C., Lambert, J.D.B., and Nomura, S. Method and apparatus for diagnosing breached fuel elements. United States: N. p., 1987. Web.
Gross, K.C., Lambert, J.D.B., & Nomura, S. Method and apparatus for diagnosing breached fuel elements. United States.
Gross, K.C., Lambert, J.D.B., and Nomura, S. Mon . "Method and apparatus for diagnosing breached fuel elements". United States.
@article{osti_6823763,
title = {Method and apparatus for diagnosing breached fuel elements},
author = {Gross, K.C. and Lambert, J.D.B. and Nomura, S.},
abstractNote = {The invention provides an apparatus and method for diagnosing breached fuel elements in a nuclear reactor. A detection system measures the activity of isotopes from the cover gas in the reactor. A data acquisition and processing system monitors the detection system and corrects for the effects of the cover-gas clean up system on the measured activity and further calculates the derivative curve of the corrected activity as a function of time. A plotting system graphs the derivative curve, which represents the instantaneous release rate of fission gas from a breached fuel element. 8 figs.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1987},
month = {3}
}