GB1309773A - Reactor fuel - Google Patents
Reactor fuelInfo
- Publication number
- GB1309773A GB1309773A GB3038070A GB3038070A GB1309773A GB 1309773 A GB1309773 A GB 1309773A GB 3038070 A GB3038070 A GB 3038070A GB 3038070 A GB3038070 A GB 3038070A GB 1309773 A GB1309773 A GB 1309773A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- sulphide
- nitride
- phosphide
- coated
- 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 abstract 3
- 239000000446 fuel Substances 0.000 abstract 10
- 239000002245 particle Substances 0.000 abstract 7
- UCKMPCXJQFINFW-UHFFFAOYSA-N Sulphide Chemical compound [S-2] UCKMPCXJQFINFW-UHFFFAOYSA-N 0.000 abstract 5
- 150000004767 nitrides Chemical class 0.000 abstract 5
- 239000002184 metal Substances 0.000 abstract 3
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 abstract 2
- 239000011248 coating agent Substances 0.000 abstract 2
- 238000000576 coating method Methods 0.000 abstract 2
- 238000000465 moulding Methods 0.000 abstract 2
- OAICVXFJPJFONN-UHFFFAOYSA-N Phosphorus Chemical compound [P] OAICVXFJPJFONN-UHFFFAOYSA-N 0.000 abstract 1
- NINIDFKCEFEMDL-UHFFFAOYSA-N Sulfur Chemical compound [S] NINIDFKCEFEMDL-UHFFFAOYSA-N 0.000 abstract 1
- 239000005864 Sulphur Substances 0.000 abstract 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 abstract 1
- 230000007797 corrosion Effects 0.000 abstract 1
- 238000005260 corrosion Methods 0.000 abstract 1
- 239000013078 crystal Substances 0.000 abstract 1
- 229910052739 hydrogen Inorganic materials 0.000 abstract 1
- 239000013067 intermediate product Substances 0.000 abstract 1
- 239000000463 material Substances 0.000 abstract 1
- 150000001247 metal acetylides Chemical class 0.000 abstract 1
- 239000000203 mixture Substances 0.000 abstract 1
- 229910052757 nitrogen Inorganic materials 0.000 abstract 1
- 229910052760 oxygen Inorganic materials 0.000 abstract 1
- 239000001301 oxygen Substances 0.000 abstract 1
- 229910052698 phosphorus Inorganic materials 0.000 abstract 1
- 239000011574 phosphorus Substances 0.000 abstract 1
- 238000005245 sintering Methods 0.000 abstract 1
- 230000000087 stabilizing effect Effects 0.000 abstract 1
- 229910052717 sulfur Inorganic materials 0.000 abstract 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 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
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
- G21C3/626—Coated fuel particles
-
- 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
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
-
- 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)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Carbon And Carbon Compounds (AREA)
- Catalysts (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Ceramic Products (AREA)
Abstract
1309773 Fuel material NUKEM NUKLEARCHEMIE UND-METALLURGIE GmbH 23 June 1970 [4 July 1969] 30380/70 Heading G6C In a nuclear fuel of UC, PuC or ThC, or mixtures of these carbides, the individual fuel carbide particles have a grain size of 0À01 to 2 mm. and are coated to a thickness of 1 to 10 microns with fuel nitride, sulphide or phosphide. Despite the low nitrogen, sulphur or phosphorus content (less than 1% by weight), these provide a stabilizing effect against water and oxygen. Since the fuel nitride, sulphide or phosphide form with the monocarbide continuous mixed crystals, it is additionally possible to prepare a single-phase nuclear fuel in the form of a modified monocarbide. One form of fuel is a sintered carbide particle, the individual crystallographic grains of fuel monocarbide each being surrounded by a coating of fuel nitride, sulphide or phosphide. An alternative form of fuel is a carbide particle surrounded by a coating of fuel nitride, sulphide or phosphide, which fuel is suitable for vibration-compacting in tubular sheaths. If the density and the corrosion resistance of the particles have to satisfy stringent requirements, the particles may be fused and in some cases coated with an addition metal or nitride, sulphide or phosphide layer. Carbide particles coated as described above may be converted under a pressure of 2 to 10 tonnes/ cm.<SP>2</SP> into mouldings with which tubular sheaths can be filled without subsequent sintering. Alternatively, carbide particles coated with a layer of metal formed as an intermediate product are converted into mouldings which are then calcined at a temperature around or above the m.p. of the metal layer and nitrided, sulphided or phosphided in a N 2 , H 2 S or H 3 P atmosphere.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE19691934031 DE1934031C3 (en) | 1969-07-04 | Carbidic nuclear fuel particles and processes for their manufacture |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1309773A true GB1309773A (en) | 1973-03-14 |
Family
ID=5738908
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB3038070A Expired GB1309773A (en) | 1969-07-04 | 1970-06-23 | Reactor fuel |
Country Status (3)
| Country | Link |
|---|---|
| BE (1) | BE752788A (en) |
| FR (1) | FR2050495B1 (en) |
| GB (1) | GB1309773A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2827071B1 (en) * | 2001-07-04 | 2003-09-05 | Commissariat Energie Atomique | PROCESS FOR SULFURING UO2 POWDER AND METHOD FOR MANUFACTURING UO2 OR MIXED OXIDE (U, PU) O2 NUCLEAR FUEL PELLETS WITH SULFUR ADDITION |
-
1969
- 1969-12-10 FR FR696942749A patent/FR2050495B1/fr not_active Expired
-
1970
- 1970-06-23 GB GB3038070A patent/GB1309773A/en not_active Expired
- 1970-06-30 BE BE752788D patent/BE752788A/en unknown
Also Published As
| Publication number | Publication date |
|---|---|
| DE1934031A1 (en) | 1971-01-07 |
| FR2050495A1 (en) | 1971-04-02 |
| DE1934031B2 (en) | 1977-06-16 |
| BE752788A (en) | 1970-12-01 |
| FR2050495B1 (en) | 1974-03-01 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PS | Patent sealed [section 19, patents act 1949] | ||
| PCNP | Patent ceased through non-payment of renewal fee |