FR2264365A1 - Metal sheath for nuclear fuel tablets - with low strength lining - Google Patents
Metal sheath for nuclear fuel tablets - with low strength liningInfo
- Publication number
- FR2264365A1 FR2264365A1 FR7507855A FR7507855A FR2264365A1 FR 2264365 A1 FR2264365 A1 FR 2264365A1 FR 7507855 A FR7507855 A FR 7507855A FR 7507855 A FR7507855 A FR 7507855A FR 2264365 A1 FR2264365 A1 FR 2264365A1
- Authority
- FR
- France
- Prior art keywords
- sheath
- axial expansion
- metal sheath
- nuclear fuel
- low strength
- 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
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/16—Details of the construction within the casing
- G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
-
- 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
- G21C3/16—Details of the construction within the casing
-
- 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)
- Laminated Bodies (AREA)
Abstract
Cylindrical fuel rod for a nuclear reactor, with a locally flexible metal sheath surrounding a number of closely in contact cylindrical fuel tables, which in novel fashion are provided with an axial expansion relief capability at the appropriate end surfaces to take up individual axial expansion during operation and avoid differential axial expansion between them and the sheath, while an intermediate layer of low shear strength, partic. graphite, siloxane or silicon is provided between the outer surface of the fuel tablets and the sheath to favour a peripheral distribution of stresses in the sheath and reduce the likelihood of longitudinal crack formation therein, which could result from local concentrations of peripheral expansion forces. Eliminates cracking of the sheath due to local deformation.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CA194,878A CA1050194A (en) | 1973-03-14 | 1974-03-13 | Terpolymers containing ester and amide linkages |
Publications (2)
Publication Number | Publication Date |
---|---|
FR2264365A1 true FR2264365A1 (en) | 1975-10-10 |
FR2264365B1 FR2264365B1 (en) | 1981-05-22 |
Family
ID=4099460
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR7507855A Granted FR2264365A1 (en) | 1974-03-13 | 1975-03-13 | Metal sheath for nuclear fuel tablets - with low strength lining |
Country Status (3)
Country | Link |
---|---|
DE (1) | DE2511054C2 (en) |
FR (1) | FR2264365A1 (en) |
SE (1) | SE402832B (en) |
Families Citing this family (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5554490A (en) * | 1978-10-17 | 1980-04-21 | Hitachi Ltd | Method of making nuclear fuel element |
IT1209773B (en) * | 1980-12-04 | 1989-08-30 | Ansaldo Mecc Nucleare | NUCLEAR FUEL TABLET WHICH PRESENTS HOT REDUCED DEFORMATIONS |
JP6352711B2 (en) * | 2014-07-22 | 2018-07-04 | 株式会社東芝 | Channel box and channel box manufacturing method |
CN115188501B (en) * | 2022-07-07 | 2024-02-06 | 中国核动力研究设计院 | Fuel rod clamping structure and positioning grid |
Family Cites Families (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1871684U (en) * | 1961-01-31 | 1963-05-09 | Siemens Ag | FUEL FOR NUCLEAR REACTORS. |
BE620961A (en) * | 1961-08-01 | |||
DE1910613U (en) * | 1964-08-29 | 1965-02-25 | Brown Boveri Krupp Reaktor | FUEL ELEMENT FOR PULSE REACTORS. |
DE2155518A1 (en) * | 1971-11-09 | 1973-05-17 | Siemens Ag | Rod type fuel element - with glass interface between fuel and cladding |
-
1975
- 1975-02-24 SE SE7502055A patent/SE402832B/en unknown
- 1975-03-13 DE DE2511054A patent/DE2511054C2/en not_active Expired
- 1975-03-13 FR FR7507855A patent/FR2264365A1/en active Granted
Also Published As
Publication number | Publication date |
---|---|
FR2264365B1 (en) | 1981-05-22 |
SE7502055L (en) | 1975-09-15 |
DE2511054A1 (en) | 1975-09-18 |
SE402832B (en) | 1978-07-17 |
DE2511054C2 (en) | 1982-08-26 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
SE7413488L (en) | ||
SE7413487L (en) | ||
JPS5397003A (en) | Thermal cracking treatment of petroleum heavy oil | |
FR2264365A1 (en) | Metal sheath for nuclear fuel tablets - with low strength lining | |
GB1454618A (en) | Nuclear fuel element | |
GB1209957A (en) | Vessel providing resistance to high pressures | |
Chan et al. | The stability of a uniformly compressed ring surrounded by a rigid circular surface | |
GB2031104A (en) | High pressure tubing | |
JPS52130409A (en) | Generating method for residual stress on the inner and outer surfaces of pipe | |
Okazaki et al. | Effect of strain wave shape on low-cycle fatigue crack propagation of SUS 304 stainless steel at elevated temperatures | |
GB978737A (en) | Improvements in fuel rods for nuclear reactors | |
JPH0557018B2 (en) | ||
US4146431A (en) | Nuclear fuel cladding system | |
TW367361B (en) | Method for reducing temperature in thermal cracking of hydrocarbons | |
Rozvany | Optimal plastic design with discontinuous cost functions | |
GB1328249A (en) | Process for manufacturing porous beta silicon-carbide articles | |
JPS5636607A (en) | Production of metal clad optical transmission body | |
EP0082660A1 (en) | Apparatus for use in liquid alkali environment | |
JPS5487637A (en) | Pressure pipe made of zirconium alloy | |
JPS5220387A (en) | Reactor | |
JPS57157003A (en) | Casing for steam turbine | |
DE905058C (en) | Process for avoiding surface cracks on centrifugal casting molds for pipes | |
US4068015A (en) | Process to minimize cracking of pyrolytic carbon coatings | |
RU2064692C1 (en) | Ventilated fuel element | |
SU968551A1 (en) | Pipeline for transportation of liquid and gas |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
ST | Notification of lapse |