GB1522531A – Method for locating defective fuel rods of a reactor fuel element
– Google Patents
GB1522531A – Method for locating defective fuel rods of a reactor fuel element
– Google Patents
Method for locating defective fuel rods of a reactor fuel element
Info
Publication number
GB1522531A
GB1522531A
GB5444/76A
GB544476A
GB1522531A
GB 1522531 A
GB1522531 A
GB 1522531A
GB 5444/76 A
GB5444/76 A
GB 5444/76A
GB 544476 A
GB544476 A
GB 544476A
GB 1522531 A
GB1522531 A
GB 1522531A
Authority
GB
United Kingdom
Prior art keywords
fuel
rods
bell
reactor
rod
Prior art date
1975-02-11
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
GB5444/76A
Inventor
Alfred Jester
Uwe Heidtmann
Hermann Birnbreier
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.)
ABB Reaktor GmbH
BBC Brown Boveri AG Germany
BBC Brown Boveri France SA
Original Assignee
Babcock Brown Boveri Reaktor GmbH
Brown Boveri und Cie AG Germany
BBC Brown Boveri France SA
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.)
1975-02-11
Filing date
1976-02-11
Publication date
1978-08-23
1976-02-11
Application filed by Babcock Brown Boveri Reaktor GmbH, Brown Boveri und Cie AG Germany, BBC Brown Boveri France SA
filed
Critical
Babcock Brown Boveri Reaktor GmbH
1978-08-23
Publication of GB1522531A
publication
Critical
patent/GB1522531A/en
Status
Expired
legal-status
Critical
Current
Links
Espacenet
Global Dossier
Discuss
Classifications
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21C—NUCLEAR REACTORS
G21C17/00—Monitoring; Testing ; Maintaining
G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
G21C17/07—Leak testing
Y—GENERAL 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
Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
Y02E30/00—Energy generation of nuclear origin
Y02E30/30—Nuclear fission reactors
Abstract
1522531 Testing fuel elements BABCOCKBROWN BOVERI REAKTOR GmbH and BROWN BOVERI & CIE AG 11 Feb 1976 [11 Feb 1975] 05444/76 Heading G6C In a method of locating leaky fuel rods within a multi-rod nuclear fuel element after irradiation in a liquid-cooled nuclear reactor, all the fuel rods are heated simultaneously at a rate sufficient to raise the temperature of a rod into which the reactor coolant has not leaked, above the boiling-point of the reactor coolant liquid, the respective temperatures of the heated fuel rods are monitored simultaneously, and any fuel rod whose temperature remains at the said boiling-point is determined to have a fault in its can through which the coolant has leaked into the rod. An apparatus for performing this method comprises a water tank 1 filled to the level 2 in which is mounted a rack 3 for accommodating a fuel element 4 which is to be tested. The rack 3 may be turned through 180 degrees so that fuel element 4 is inverted. A bell 5 is moved sideways in the broken line position while the rack 3 is being manipulated, the interior of the bell being kept dry by a stream of hot gas discharged from pipes 15. This prevents the formation of vapour in the bell 5, which vapour could endanger the functioning of a conventional thermographic infra-red measuring apparatus 6 mounted in the bell. The bell 5 is then moved by a crab (not shown) into the solid-line position. The rack 3 is raised by a lifting device (not shown) so that the fuel rods project by 30-100 mm. above the water level N in the ball 5. Fig. 2 shows an end region of a fuel rod 22 with a capillary structure 12 comprising a metal mesh, fleece or felt or a porous ceramic slug disposed in a cavity 21 in the end cap 11. Cooling water leaks during reactor operation into all defective fuel rods and collects in their bottom region after reactor shut-down. The capillary structure 12 in a leaky fuel rod becomes charged with water and, after the rack 3 is turned through 180 degrees, is disposed in the end cap 11 which projects into the bell 5. An alternative construction is shown in Fig. 3 in which a cup-shaped cap 19 of sheet metal is located in the end cap 11, open towards the end, and formed with a central port 20 for drainage of excess water on inversion of the fuel element. In a further construction (Fig. 4, not shown), a wick (24) projects through the fission gas space 25 as far as the fuel pellets 10 to convey any leakage water into the capillary structure 12. Such a fuel rod is tested without inversion, e.g. in situ in the reactor core. Heat radiation sources 15 disposed in the bell 5, and/or the hot gas discharged from pipes 15, uniformly heat the end faces of the end caps 11. During the time which elapses before any leakage water has evaporated, the absorption of latent heat of evaporation will cause the temperature of the end cap end faces to be maintained at 100 C. The heat radation sources 14 are able to heat the end cap end faces of non-defective rods to at least 125 C., the temperature difference #25 C. being detected by the infra-red temperature measuring apparatus 6. A monitor 16 connected to the apparatus 6 enables the positions of all defective rods to be located at a glance, defective rods appearing as dark areas 17 and non- defective rods as bright areas 18.
GB5444/76A
1975-02-11
1976-02-11
Method for locating defective fuel rods of a reactor fuel element
Expired
GB1522531A
(en)
Applications Claiming Priority (1)
Application Number
Priority Date
Filing Date
Title
DE2505645A
DE2505645C2
(en)
1975-02-11
1975-02-11
Method for locating defective fuel rods in a reactor fuel assembly
Publications (1)
Publication Number
Publication Date
GB1522531A
true
GB1522531A
(en)
1978-08-23
Family
ID=5938578
Family Applications (1)
Application Number
Title
Priority Date
Filing Date
GB5444/76A
Expired
GB1522531A
(en)
1975-02-11
1976-02-11
Method for locating defective fuel rods of a reactor fuel element
Country Status (12)
Country
Link
US
(1)
US4079620A
(en)
JP
(1)
JPS51116395A
(en)
AT
(1)
AT362027B
(en)
BR
(1)
BR7600813A
(en)
CH
(1)
CH607239A5
(en)
DE
(1)
DE2505645C2
(en)
ES
(1)
ES444800A1
(en)
FR
(1)
FR2301073A1
(en)
GB
(1)
GB1522531A
(en)
IL
(1)
IL48974A
(en)
IT
(1)
IT1053971B
(en)
SE
(1)
SE423162B
(en)
Families Citing this family (8)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
DE2635501C2
(en)
*
1976-08-06
1986-01-09
Kraftwerk Union AG, 4330 Mülheim
Fuel rod replacement tool
FR2460027A1
(en)
*
1979-06-26
1981-01-16
Framatome Sa
PROCESS FOR HANDLING COMBUSTIBLE ASSEMBLIES AND PENS WHEN RECHARGING A NUCLEAR REACTOR
FR2493025B1
(en)
*
1980-10-24
1986-04-18
Framatome Sa
METHOD AND DEVICE FOR DETECTING DEFECTIVE FUEL ELEMENTS IN A FUEL ASSEMBLY FOR A NUCLEAR REACTOR
US4522780A
(en)
*
1982-02-16
1985-06-11
Westinghouse Electric Corp.
Removal and replacement of fuel rods in nuclear fuel assembly
US4643866A
(en)
*
1983-08-24
1987-02-17
The Babcock & Wilcox Company
Nuclear fuel pellet-cladding interaction test device and method modeling in-core reactor thermal conditions
US4864847A
(en)
*
1985-05-29
1989-09-12
The United States Of America As Represented By The Administrator Of The National Aeronautics And Space Administration
Fluid leak indicator
US8811563B2
(en)
*
2004-12-30
2014-08-19
General Electric Company
Method and system for assessing failures of fuel rods
US8842796B2
(en)
*
2011-11-22
2014-09-23
Westinghouse Electric Company Llc
Nuclear fuel rod pellet stack inspection
Family Cites Families (8)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
DE1093501B
(en)
*
1959-03-28
1960-11-24
Forschungslaboratorium Prof Dr
Procedure for observing, measuring and regulating the temperature of nuclear reactors
SE320516B
(en)
*
1967-09-26
1970-02-09
Bofors Ab
US3526135A
(en)
*
1967-12-29
1970-09-01
Garrett Corp
Temperature detecting system
US3801441A
(en)
*
1971-10-12
1974-04-02
Transfer Systems
Failed nuclear reactor fuel detection apparatus
US3940313A
(en)
*
1972-04-03
1976-02-24
Siemens Aktiengesellschaft
Device for detecting defective nuclear reactor fuel rods
US3936348A
(en)
*
1973-02-05
1976-02-03
Wesley M. Rohrer
Method and apparatus for detection of nuclear fuel rod failures
DE2314650C3
(en)
*
1973-03-23
1978-10-12
Kraftwerk Union Ag, 4330 Muelheim
Method and device for finding defective fuel rods
US3878040A
(en)
*
1973-09-20
1975-04-15
Combustion Eng
Failed fuel detector
1975
1975-02-11
DE
DE2505645A
patent/DE2505645C2/en
not_active
Expired
1976
1976-01-28
CH
CH105776A
patent/CH607239A5/xx
not_active
IP Right Cessation
1976-01-30
ES
ES444800A
patent/ES444800A1/en
not_active
Expired
1976-02-05
AT
AT79376A
patent/AT362027B/en
not_active
IP Right Cessation
1976-02-05
IL
IL48974A
patent/IL48974A/en
unknown
1976-02-09
US
US05/656,275
patent/US4079620A/en
not_active
Expired – Lifetime
1976-02-10
IT
IT48039/76A
patent/IT1053971B/en
active
1976-02-10
BR
BR7600813A
patent/BR7600813A/en
unknown
1976-02-10
FR
FR7603658A
patent/FR2301073A1/en
active
Granted
1976-02-10
SE
SE7601418A
patent/SE423162B/en
unknown
1976-02-10
JP
JP51012917A
patent/JPS51116395A/en
active
Pending
1976-02-11
GB
GB5444/76A
patent/GB1522531A/en
not_active
Expired
Also Published As
Publication number
Publication date
DE2505645C2
(en)
1982-06-24
DE2505645A1
(en)
1976-08-19
AT362027B
(en)
1981-04-27
SE423162B
(en)
1982-04-13
SE7601418L
(en)
1976-08-12
FR2301073B1
(en)
1980-03-07
FR2301073A1
(en)
1976-09-10
IL48974A0
(en)
1976-04-30
IT1053971B
(en)
1981-10-10
ES444800A1
(en)
1977-11-01
IL48974A
(en)
1979-07-25
BR7600813A
(en)
1976-08-31
CH607239A5
(en)
1978-11-30
US4079620A
(en)
1978-03-21
ATA79376A
(en)
1980-09-15
JPS51116395A
(en)
1976-10-13
Similar Documents
Publication
Publication Date
Title
US4016749A
(en)
1977-04-12
Method and apparatus for inspection of nuclear fuel rods
CN104034651B
(en)
2016-04-06
The Special experimental apparatus of used in nuclear power station cladding materials Evaluation of Corrosion Resistance in high-temperature steam
US3945245A
(en)
1976-03-23
Method and equipment for detecting deflective nuclear fuel rods
MX3235E
(en)
1980-08-05
IMPROVEMENTS IN A METHOD AND APPARATUS TO DISCOVER DEFECTIVE NUCLEAR FUEL ELEMENTS IN WATER MODERATED REACTORS
GB1522531A
(en)
1978-08-23
Method for locating defective fuel rods of a reactor fuel element
US3419467A
(en)
1968-12-31
Method of and apparatus for locating envelope-tube damage at individual nuclear fuel elements in a reactor core
CN108091409A
(en)
2018-05-29
A kind of nuclear emergency set state diagnosis and the comprehensive estimation method of damage sequence
Cohen et al.
1961
Measurement of the thermal conductivity of metal clad uranium oxide rods during irradiation
US3983741A
(en)
1976-10-05
Method and apparatus for locating defective fuel rods in a reactor fuel assembly
US3497421A
(en)
1970-02-24
Shielded enclosure providing resistance to high temperatures and pressures
Takeda
2019
Helium leak detection method using ambient temperature of canister top
ES405462A1
(en)
1975-07-16
Detecting leaks in heat-insulated reservoirs
US3719555A
(en)
1973-03-06
Irradiation test facility
Somfai et al.
2018
Experimental simulation of activity release from leaking fuel rods
JPS5931030B2
(en)
1984-07-30
Nuclear reactor fuel element damage inspection device
Rasneur et al.
1992
Irradiation behavior of LiAlO2 and Li2ZrO3 ceramics in the ALICE 3 experiment
RU2094861C1
(en)
1997-10-27
Method for detecting depressurized fuel elements
US3442118A
(en)
1969-05-06
Device for testing a body of fluid
KR820000833B1
(en)
1982-05-13
Crack detection ceil for checking the leak prootness of fuel element units
SU578570A1
(en)
1977-10-30
Device for dissoving solid bodies in hightemperature kalve's type microcalorimeters
JP2020525799A
(en)
2020-08-27
Analyzer for detecting fission products by measuring radioactivity
SU938089A1
(en)
1982-06-23
Device for measuring temperature in testing thin-walled tubular specimen by inner gas pressure
Verrall
1990
CRITIC-I tritium release and post irridiation examination of large-grained lithium oxide
JPS5934196A
(en)
1984-02-24
Fuel sipping device
Roy et al.
1975
Hydrogen detector for sodium cooled reactors
Legal Events
Date
Code
Title
Description
1978-12-20
PS
Patent sealed [section 19, patents act 1949]
1982-09-08
PCNP
Patent ceased through non-payment of renewal fee
