GB1531120A - Testing nuclear fuel rods - Google Patents
Testing nuclear fuel rodsInfo
- Publication number
- GB1531120A GB1531120A GB39006/77A GB3900677A GB1531120A GB 1531120 A GB1531120 A GB 1531120A GB 39006/77 A GB39006/77 A GB 39006/77A GB 3900677 A GB3900677 A GB 3900677A GB 1531120 A GB1531120 A GB 1531120A
- Authority
- GB
- United Kingdom
- Prior art keywords
- end cap
- fuel rods
- water
- nuclear fuel
- fuel
- 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.)
- Expired
Links
- 239000003758 nuclear fuel Substances 0.000 title 1
- 239000000446 fuel Substances 0.000 abstract 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 3
- 238000005253 cladding Methods 0.000 abstract 1
- 230000002950 deficient Effects 0.000 abstract 1
- 238000010438 heat treatment Methods 0.000 abstract 1
- 230000002706 hydrostatic effect Effects 0.000 abstract 1
- 230000002123 temporal effect Effects 0.000 abstract 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/10—End closures ; Means for tight mounting therefor
-
- 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
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)
Abstract
In order to detect defective fuel rods in fuel elements of water cooled nuclear reactors, the fuel elements are firstly subjected to a hydrostatic alternating pressure treatment. The cladding tubes of the fuel rods are then heated in the vicinity of an accessible end cap, resulting in heating of the water situated in said end cap in the event of damage. The presence of water is established by measuring the temporal temperature characteristic at the end cap or by applying ultrasonic pulses to the end cap and evaluating the echo pulses.
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 |
---|---|
GB1531120A true GB1531120A (en) | 1978-11-01 |
Family
ID=5988316
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB39006/77A Expired GB1531120A (en) | 1976-09-20 | 1977-09-19 | Testing nuclear fuel rods |
Country Status (4)
Country | Link |
---|---|
JP (1) | JPS5352895A (en) |
CH (1) | CH607802A5 (en) |
DE (1) | DE2642156A1 (en) |
GB (1) | GB1531120A (en) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2454675A1 (en) * | 1979-04-20 | 1980-11-14 | Framatome Sa | METHOD FOR CONTROLLING FUEL PENCILS FOR ASSEMBLIES FOR NUCLEAR REACTOR AND DEVICE THEREOF |
FR2466082A1 (en) * | 1979-09-26 | 1981-03-27 | Framatome Sa | METHOD OF ACOUSTICALLY AND ULTRASONICALLY DETECTING COMBUSTIBLE ASSEMBLIES OF A NUCLEAR REACTOR WHICH HAVE BEEN DEFECTIVE IN SERVICE AND CORRESPONDING DETECTION DEVICE |
-
1976
- 1976-09-20 DE DE19762642156 patent/DE2642156A1/en not_active Ceased
-
1977
- 1977-07-28 CH CH931777A patent/CH607802A5/en not_active IP Right Cessation
- 1977-09-19 GB GB39006/77A patent/GB1531120A/en not_active Expired
- 1977-09-20 JP JP11314777A patent/JPS5352895A/en active Pending
Also Published As
Publication number | Publication date |
---|---|
DE2642156A1 (en) | 1978-03-23 |
JPS5352895A (en) | 1978-05-13 |
CH607802A5 (en) | 1978-10-31 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
SE7701422L (en) | PROCEDURE AND DEVICE FOR DETECTING DEFECTIVE FUEL RODS IN NUCLEAR REACTOR | |
ATA853476A (en) | TEST SYSTEM SUPPORT FOR TESTING THE CONNECTION AREA OF PRESSURE TANK, IN PARTICULAR REACTOR PRESSURE TANK OF NUCLEAR POWER PLANTS, WITH ULTRASOUND | |
ES8301552A1 (en) | Method and apparatus for the control of fuel rods used in nuclear reactor assemblies. | |
ES8404096A1 (en) | Method and device for detecting defective fuel elements in a nuclear reactor fuel assembly. | |
ES8608716A1 (en) | Device for checking the coolant condition in a nuclear reactor. | |
SE7407494L (en) | ENZYME THERMISTOR | |
GB1531120A (en) | Testing nuclear fuel rods | |
ATE32283T1 (en) | METHOD AND EQUIPMENT FOR LOCATING DEFECTIVE FUEL TUBE IN WATER-COOLED NUCLEAR REACTORS. | |
FR2307341A1 (en) | Core power density locally measured - by external neutron flux chambers installed inside core | |
ES9200013A1 (en) | Testing pellet-cladding interaction. | |
ES420657A1 (en) | Detection of leakage of fluid from nuclear reactor | |
GB1275887A (en) | A creep cell which is primarily intended for use in nuclear reactors | |
FR2372495A1 (en) | NUCLEAR REACTOR AND METHOD FOR DETERMINING THE POWER DISTRIBUTION IN A REACTOR CORE | |
YU122478A (en) | Unltrasonic calibration device for use in connection with transducers of an arrangement for checking the nuclear reactor vessel | |
Emery et al. | Effects of Heating Rate and Pressure on Expansion of Zircaloy Tubing During Sudden Heating Conditions | |
GB1323076A (en) | Leak detecting instruments | |
IT1047427B (en) | DEVICE FOR THE DETECTION OF LEAKS IN THE FUEL BARS OF NUCLEAR REACTORS | |
FR2341182A1 (en) | Localising deflective nuclear reactor combustible elements - using sonic and ultrasonic signals from transducer on element | |
WYLIE | In-service inspection program for nuclear reactor vessels(Power reactor technology, reactor inspections, and reactor safety)[Semiannual Progress Report, 1 Sep. 1970- 1 Mar. 1971] | |
Sakae et al. | Relation Between the Corrosion Resistance and Heat Treatment of 405 Ferritic Stainless Steel | |
PIERGALLINI et al. | Optical effects of pigmentation of temperature rise in a two-layer skin simulant system during irradiation[Interim Report] | |
RU94037398A (en) | Method for detecting unsealed fuel elements | |
AT285209B (en) | Device for non-destructive testing of hot workpieces with ultrasound | |
SE8401937L (en) | METHOD DEVICE FOR DETERMINING THE PRESSURE IN Fission GAS RELEASED IN NUCLEAR FUEL RODS | |
MCCLUNG | Nondestructive testing of irradiated fuel elements in the United States of America(Nondestructive testing of irradiated fuel elements) |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed [section 19, patents act 1949] | ||
PCNP | Patent ceased through non-payment of renewal fee |