FR2266939A2 - Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces - Google Patents
Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small piecesInfo
- Publication number
- FR2266939A2 FR2266939A2 FR7411821A FR7411821A FR2266939A2 FR 2266939 A2 FR2266939 A2 FR 2266939A2 FR 7411821 A FR7411821 A FR 7411821A FR 7411821 A FR7411821 A FR 7411821A FR 2266939 A2 FR2266939 A2 FR 2266939A2
- Authority
- FR
- France
- Prior art keywords
- fuel
- zircalloy
- fuel element
- cladded
- cladding
- 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.)
- Granted
Links
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
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/36—Assemblies of plate-shaped fuel elements or coaxial tubes
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Manufacturing & Machinery (AREA)
- Laminated Bodies (AREA)
Abstract
The minimise the escape of radio-active fission prods. in the event of a fuel element wall leak, plate type elements are made up of many uniform shaped pieces of fuel matl. each wrapped separately. Various methods of wrapping are proposed. The assembled pieces making up the fuel element are wrapped overall and a good heat-transfer bond achieved between fuel and cladding by high temp. fusion welding. E.g. with zirconium alloy cladding and ceramic fuel matl. the assembled element is heated for 4 hours at 830 degrees and 2,000 atm pressure in Helium. The internal wrapping is e.g. 0.4 mm and the main cladding 4 mm zircalloy.
Priority Applications (10)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7411821A FR2266939A2 (en) | 1974-04-03 | 1974-04-03 | Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces |
GB2856674A GB1445269A (en) | 1973-07-06 | 1974-06-27 | Emthod of fabrication of a ceramic nuclear fuel element |
SE7408480D SE7408480L (en) | 1973-07-06 | 1974-06-27 | |
CH890474A CH590541A5 (en) | 1973-07-06 | 1974-06-28 | |
NL7408987A NL7408987A (en) | 1973-07-06 | 1974-07-03 | PLATE-SHAPED NUCLEAR FLEXIBLE ELEMENT AND METHOD FOR MANUFACTURING IT. |
IT69150/74A IT1014475B (en) | 1973-07-06 | 1974-07-05 | NUCLEAR FUEL ELEMENT AND PROCEDURE FOR ITS FACTORY |
JP49077242A JPS5744958B2 (en) | 1973-07-06 | 1974-07-05 | |
DE2432407A DE2432407A1 (en) | 1973-07-06 | 1974-07-05 | PLATE-SHAPED NUCLEAR FUEL ELEMENT AND METHOD OF MANUFACTURING THE SAME |
ES428051A ES428051A1 (en) | 1973-07-06 | 1974-07-06 | Emthod of fabrication of a ceramic nuclear fuel element |
US05/727,730 US4038135A (en) | 1973-07-06 | 1976-09-29 | Plate type nuclear fuel element and a method of fabrication of said element |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7411821A FR2266939A2 (en) | 1974-04-03 | 1974-04-03 | Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces |
Publications (2)
Publication Number | Publication Date |
---|---|
FR2266939A2 true FR2266939A2 (en) | 1975-10-31 |
FR2266939B2 FR2266939B2 (en) | 1978-11-03 |
Family
ID=9137233
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR7411821A Granted FR2266939A2 (en) | 1973-07-06 | 1974-04-03 | Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces |
Country Status (1)
Country | Link |
---|---|
FR (1) | FR2266939A2 (en) |
-
1974
- 1974-04-03 FR FR7411821A patent/FR2266939A2/en active Granted
Also Published As
Publication number | Publication date |
---|---|
FR2266939B2 (en) | 1978-11-03 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
ES446545A1 (en) | Getter for nuclear fuel elements | |
GB790389A (en) | Improvements in or relating to fuel elements for use in nuclear reactors | |
FR2236250A1 (en) | Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces | |
FR2266939A2 (en) | Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces | |
GB2004074B (en) | Method for verifying the pressure in a nuclear reactor fuel rod | |
ES472678A1 (en) | Method for protecting the casing tubes of nuclear reactor fuel rods | |
JPS5619494A (en) | Method of positioning leaked fuel rod in nuclear fuel assembly | |
JPS57182197A (en) | Device for protecting leakage of fissionable gas in nuclear fuel rod | |
GB829139A (en) | Improvements in or relating to nuclear reactor fuel elements | |
Notley | Calculation of Fission-Product Gas Pressures in Operating UO2 Fuel Elements | |
GB989393A (en) | Improvements in or relating to nuclear reactor fuel elements | |
GB1493090A (en) | Tritium removal and retention device | |
Keegstra et al. | Finite Element Stress Analysis of Interacting Fuel Pellet and Canning under Fast Reactor Condition | |
GB1445269A (en) | Emthod of fabrication of a ceramic nuclear fuel element | |
IT1137284B (en) | PROCEDURE FOR MANUFACTURING ZIRCONIUM ALLOY PIPES INTENDED FOR USE IN REACTORS AND NUCLEAR ENERGY | |
GB860190A (en) | Improvements relating to pressure vessels | |
GB1539241A (en) | Method of determining the locality of one or more defective fuel elements in a nuclear reactor core | |
BENSKY et al. | Spent fuel storage and isolation(Conferences) | |
GRANDO et al. | Fast reactor sodium bonded fuel rod evaluation in a thermal reactor(Radiation testing of sodium-bonded, fast reactor PuC-UC fuel rods at high burnup in thermal reactors) | |
KAEMPF et al. | Treatment of the mechanical and thermal relations of fuel rods in Saturn 1(Calculating time history of fuel pin concerning radial distribution of temperature, stress, porosity and geometry changes in Saturn 1) | |
BAUER et al. | Evaluating strength and ductility of irradiated zircaloy, task 5(nuclear fuel claddings)[Quarterly Progress Report, Jan.- Mar. 1978] | |
JPS5234191A (en) | Nuclear fuel element | |
CA801298A (en) | Nuclear reactor fuel rod with positive thermal expansion coefficient of reactivity | |
JPS6484187A (en) | Method for reassembling fuel assembly | |
Reynolds | Measurement of Free Fission-Gas Pressure in Operating UO2-Filled Fuel Rods |