SE9500972L - Fuel capsule with depletion areas adjacent to zirconium barriers - Google Patents
Fuel capsule with depletion areas adjacent to zirconium barriersInfo
- Publication number
- SE9500972L SE9500972L SE9500972A SE9500972A SE9500972L SE 9500972 L SE9500972 L SE 9500972L SE 9500972 A SE9500972 A SE 9500972A SE 9500972 A SE9500972 A SE 9500972A SE 9500972 L SE9500972 L SE 9500972L
- Authority
- SE
- Sweden
- Prior art keywords
- substrate
- zirconium
- barriers
- areas adjacent
- fuel capsule
- Prior art date
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
- G21C3/06—Casings; Jackets
- G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
-
- 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
A novel cladding tube has a cross-section comprising (a) an outer substrate of Zr alloy; (b) a depletion region which extends into the substrate from its inner surface and which has a thickness of more than 10 microns and an alloying element concn. much lower than that in the substrate region outside the depletion region; and (c) a zirconium barrier layer which is bonded to the inner surface of the substrate and which has, at its inner surface, an alloying element concn. sufficient to withstand accelerated corrosion. Also claimed is a process for prodn. of a zircalloy cladding tube for holding fissile material in water cooled nuclear fission reactors.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US21545294A | 1994-03-21 | 1994-03-21 |
Publications (2)
Publication Number | Publication Date |
---|---|
SE9500972D0 SE9500972D0 (en) | 1995-03-20 |
SE9500972L true SE9500972L (en) | 1995-09-22 |
Family
ID=22803036
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
SE9500972A SE9500972L (en) | 1994-03-21 | 1995-03-20 | Fuel capsule with depletion areas adjacent to zirconium barriers |
Country Status (3)
Country | Link |
---|---|
JP (1) | JPH0821888A (en) |
DE (1) | DE19509407A1 (en) |
SE (1) | SE9500972L (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP3401924B1 (en) * | 2017-05-12 | 2019-12-11 | Westinghouse Electric Sweden AB | A nuclear fuel pellet, a fuel rod, and a fuel assembly |
-
1995
- 1995-03-15 DE DE19509407A patent/DE19509407A1/en not_active Withdrawn
- 1995-03-20 JP JP7060177A patent/JPH0821888A/en not_active Withdrawn
- 1995-03-20 SE SE9500972A patent/SE9500972L/en not_active Application Discontinuation
Also Published As
Publication number | Publication date |
---|---|
DE19509407A1 (en) | 1995-09-28 |
JPH0821888A (en) | 1996-01-23 |
SE9500972D0 (en) | 1995-03-20 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
SE8801246L (en) | IMPROVED NUCLEAR FUEL ELEMENT | |
ES2107131T3 (en) | ZIRCALOY PIPE THAT HAS GREAT RESISTANCE TO THE SPREAD OF CRACKS. | |
KR920009646B1 (en) | Zirconium alloy fuel cladding resistant to pci crack propagation | |
KR100279916B1 (en) | Elliptical metal fuel / cladding barriers and related heat transfer enhancement methods | |
IT1110295B (en) | NON-EVAPORABLE TERNARY GETTERING ALLOY PARTICULARLY FOR THE ABSORPTION OF WATER AND WATER VAPOR IN FUEL BARS OF NUCLEAR REACTORS | |
SE9500971D0 (en) | Improved zirconium alloy fuel cladding | |
SE9500968L (en) | Nuclear fuel capsule with an alloy zirconium barrier layer | |
US4971753A (en) | Nuclear fuel element, and method of forming same | |
SE8902924L (en) | FOERBAETTRAT KAERNBRAENSLEELEMENT | |
BE903252A (en) | NEUTRON SHIELDING PANEL FOR A NUCLEAR REACTOR PRESSURE TANK | |
US4613479A (en) | Water reactor fuel cladding | |
SE510281C2 (en) | Nuclear fuel capsule with a hydrogen-absorbing inner lining | |
SE9500972L (en) | Fuel capsule with depletion areas adjacent to zirconium barriers | |
SE8300016D0 (en) | Zirconium alloy barriers with improved corrosion resistance | |
SE8301815D0 (en) | Zirconium alloy barriers with improved corrosion resistance | |
SE9402593D0 (en) | Thermomechanical treatment of composite enclosure for nuclear fuel elements | |
KR930005573B1 (en) | Hydride blister-resistant zirconium based nuclear fuel rod cladding | |
SE8302484L (en) | OVERVIEW Zirconium layer | |
WO2001082306A3 (en) | Method of incineration of minor actinides in nuclear reactors | |
Takahashi et al. | Overview of recent studies related to lead-alloy-cooled fast reactors | |
Pilch et al. | Preliminary calculations on direct heating of a containment atmosphere by airborne core debris | |
SE8204812D0 (en) | NUCLEAR FUEL ELEMENTS AND MANUFACTURING THEREOF | |
TW258815B (en) | Nuclear fuel cladding having a gold coating | |
Seidel et al. | A decade of advances in metallic fuel | |
RU2105359C1 (en) | Nuclear reactor fuel element |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
NAV | Patent application has lapsed |
Ref document number: 9500972-6 |