FR2236250A1 - 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
- FR2236250A1 FR2236250A1 FR7324992A FR7324992A FR2236250A1 FR 2236250 A1 FR2236250 A1 FR 2236250A1 FR 7324992 A FR7324992 A FR 7324992A FR 7324992 A FR7324992 A FR 7324992A FR 2236250 A1 FR2236250 A1 FR 2236250A1
- 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
- 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
-
- 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
-
- 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 (12)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7324992A FR2236250A1 (en) | 1973-07-06 | 1973-07-06 | 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 | |
BE146034A BE817036A (en) | 1973-07-06 | 1974-06-28 | PLATE NUCLEAR FUEL ELEMENT AND ITS MANUFACTURING PROCESS |
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 |
FR7710433A FR2386887A2 (en) | 1973-07-06 | 1977-04-06 | Nuclear fuel element in ceramic material - comprises metal frame forming enclosed compartments for fuel platelets, and is economical to make and mechanically strong |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7324992A FR2236250A1 (en) | 1973-07-06 | 1973-07-06 | Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces |
Publications (2)
Publication Number | Publication Date |
---|---|
FR2236250A1 true FR2236250A1 (en) | 1975-01-31 |
FR2236250B1 FR2236250B1 (en) | 1978-09-29 |
Family
ID=9122228
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR7324992A Granted FR2236250A1 (en) | 1973-07-06 | 1973-07-06 | Nuclear fuel element plates eg zircalloy cladded - divided internally into separately wrapped small pieces |
Country Status (2)
Country | Link |
---|---|
BE (1) | BE817036A (en) |
FR (1) | FR2236250A1 (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2023280897A1 (en) * | 2021-07-06 | 2023-01-12 | Framatome | Method for manufacturing a nuclear fuel element, and nuclear fuel element |
-
1973
- 1973-07-06 FR FR7324992A patent/FR2236250A1/en active Granted
-
1974
- 1974-06-28 BE BE146034A patent/BE817036A/en not_active IP Right Cessation
Non-Patent Citations (1)
Title |
---|
NEANT * |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2023280897A1 (en) * | 2021-07-06 | 2023-01-12 | Framatome | Method for manufacturing a nuclear fuel element, and nuclear fuel element |
FR3125164A1 (en) * | 2021-07-06 | 2023-01-13 | Framatome | Process for manufacturing a nuclear fuel element and nuclear fuel element |
Also Published As
Publication number | Publication date |
---|---|
FR2236250B1 (en) | 1978-09-29 |
BE817036A (en) | 1974-10-16 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
GB840753A (en) | Plates with oxide inserts | |
GB933500A (en) | Nuclear fuel element | |
GB859395A (en) | Nuclear reactors containing fuel elements | |
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 | |
GB829139A (en) | Improvements in or relating to nuclear reactor fuel elements | |
GB1445269A (en) | Emthod of fabrication of a ceramic nuclear fuel element | |
IT8122790A0 (en) | PROCEDURE FOR MANUFACTURING ZIRCONIA ALLOY TUBES INTENDED FOR USE IN REACTORS AND NUCLEAR ENERGY. | |
JPS5215995A (en) | Nuclear fusion reactor | |
GB1493090A (en) | Tritium removal and retention device | |
GB860190A (en) | Improvements relating to pressure vessels | |
GB873370A (en) | Improvements in or relating to fuel elements for nuclear reactors | |
GB1469909A (en) | Method of fabrication of nuclear fuel compacts | |
IT1172858B (en) | PROCEDURE FOR RECHARGING THE FUEL IN A NUCLEAR HOT WATER NUCLEAR REACTOR | |
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) | |
JPS6484187A (en) | Method for reassembling fuel assembly | |
CA801298A (en) | Nuclear reactor fuel rod with positive thermal expansion coefficient of reactivity | |
BENSKY et al. | Spent fuel storage and isolation(Conferences) | |
JPS5234191A (en) | Nuclear fuel element | |
GB1302319A (en) | ||
WHITMARSH | Neutronics analysis of an open-cycle high-impulse gas core reactor concept(Calculation of critical fuel mass for coaxial-flow gas-core reactors for specific conditions of operation) | |
CA978668A (en) | Method of inserting nuclear fuel rods in grid assembly |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
ST | Notification of lapse |