GB1206927A - Particulate nuclear fuels - Google Patents
Particulate nuclear fuelsInfo
- Publication number
- GB1206927A GB1206927A GB08344/69A GB1834469A GB1206927A GB 1206927 A GB1206927 A GB 1206927A GB 08344/69 A GB08344/69 A GB 08344/69A GB 1834469 A GB1834469 A GB 1834469A GB 1206927 A GB1206927 A GB 1206927A
- Authority
- GB
- United Kingdom
- Prior art keywords
- layer
- fuel
- particles
- group
- groups
- 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 1
- 239000000446 fuel Substances 0.000 abstract 11
- 239000002245 particle Substances 0.000 abstract 8
- 239000000463 material Substances 0.000 abstract 6
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 abstract 5
- 229910010271 silicon carbide Inorganic materials 0.000 abstract 5
- 229910052751 metal Inorganic materials 0.000 abstract 3
- 239000002184 metal Substances 0.000 abstract 3
- 238000000034 method Methods 0.000 abstract 3
- 230000003647 oxidation Effects 0.000 abstract 3
- 238000007254 oxidation reaction Methods 0.000 abstract 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 abstract 2
- 238000012993 chemical processing Methods 0.000 abstract 2
- 230000004992 fission Effects 0.000 abstract 2
- 229910002804 graphite Inorganic materials 0.000 abstract 2
- 239000010439 graphite Substances 0.000 abstract 2
- 230000014759 maintenance of location Effects 0.000 abstract 2
- 229910052770 Uranium Inorganic materials 0.000 abstract 1
- 239000010419 fine particle Substances 0.000 abstract 1
- 239000011159 matrix material Substances 0.000 abstract 1
- 239000002296 pyrolytic carbon Substances 0.000 abstract 1
- 238000012216 screening Methods 0.000 abstract 1
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 abstract 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/07—Pebble-bed reactors; Reactors with granular fuel
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01J—CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
- B01J2/00—Processes or devices for granulating materials, e.g. fertilisers in general; Rendering particulate materials free flowing in general, e.g. making them hydrophobic
- B01J2/006—Coating of the granules without description of the process or the device by which the granules are obtained
-
- 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
-
- 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)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Ceramic Engineering (AREA)
- Organic Chemistry (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Carbon And Carbon Compounds (AREA)
Abstract
1,206,927. Treatment of spent fuel; reactors. GULF GENERAL ATOMIC Inc. 10 April, 1969 [25 April, 1968 (2)], No. 18344/69. Headings G6C and G6R. A reactor employs particulate fuel material comprising at least two groups, the particles of each group being coated with a fission product retention layer, that layer in one group being constituted by silicon carbide and in the other group by dense metal carbide or pyrocarbon which is less oxidation resistant than silicon carbide. Thus, after burnup in the reactor the two groups may be separated from each other, prior to chemical processing of the fuel, by subjecting the mixed particles to an oxidation process, this process causing removal of the dense metal carbide or pyrocarbon layer and reducing this group of fuel material to an ash or fine particle size whereas the silicon carbide layer is not removed and the particles of this group remain intact. Mechanical screening is then used to separate the two groups. Generally, the fuel material of the two groups would be different and require different chemical processing. In particular, one group comprises fissile fuel material in the form of uranium dicarbide and these particles are coated with a silicon carbide layer. The other group comprises primarily fertile material in the form of thoriumuranium dioxide or carbide and these particles are coated with a dense metal carbide or pyrocarbon layer. In both groups the fuel particles may have a layer of low density spongy pyrolytic carbon deposited directly on the fuel material and situated beneath the fission product retention layer. In one arrangement the silicon carbide layer is coated with a layer of dense pyrocarbon, this latter layer being removed in the oxidation process. The fuel particles may be loosely loaded into chambers of graphite block fuel elements or may be bonded together in those chambers by pitch. Alternatively, the fuel particles may be combined with a graphite matrix material and formed with pitch into a fuel body.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US72424468A | 1968-04-25 | 1968-04-25 | |
| US72424868A | 1968-04-25 | 1968-04-25 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1206927A true GB1206927A (en) | 1970-09-30 |
Family
ID=27110953
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB08344/69A Expired GB1206927A (en) | 1968-04-25 | 1969-04-10 | Particulate nuclear fuels |
Country Status (9)
| Country | Link |
|---|---|
| AT (1) | AT330906B (en) |
| BE (1) | BE731955A (en) |
| CA (1) | CA918317A (en) |
| CH (1) | CH498470A (en) |
| DE (1) | DE1920387A1 (en) |
| FR (1) | FR2006915A1 (en) |
| GB (1) | GB1206927A (en) |
| NL (1) | NL6905948A (en) |
| SE (1) | SE343163B (en) |
Families Citing this family (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CH660352A5 (en) * | 1983-04-26 | 1987-04-15 | Fischer Ag Brugg Georg | STORAGE DEVICE FOR PLATE-SHAPED WORKPIECES. |
| DE4134746C2 (en) * | 1990-11-02 | 1996-01-18 | Kannegiesser H Gmbh Co | Method and device for stacking folded laundry items |
| DE4213201A1 (en) * | 1992-04-22 | 1993-10-28 | Will E C H Gmbh & Co | Conveyor system for moving stacks of paper sheets - has reject sluice for faulty stacks set between two conveyors to avoid unnecessary handling and wastage of wrapping materials. |
| DE4219982A1 (en) * | 1992-06-19 | 1993-12-23 | Kolbus Gmbh & Co Kg | Stacking device for books |
| DE4328460A1 (en) * | 1993-08-24 | 1995-03-02 | Meyer Herbert Gmbh Co Kg | Method and arrangement for the destacking of sheet-like workpieces |
| DE4328461A1 (en) * | 1993-08-24 | 1995-03-02 | Meyer Herbert Gmbh Co Kg | Method and arrangement for conveying flat workpieces |
| DE9418577U1 (en) * | 1994-11-22 | 1995-01-05 | Icoma Packtechnik Gmbh, 77855 Achern | Palletizer |
| PL3437106T3 (en) * | 2016-03-29 | 2021-07-12 | Ultra Safe Nuclear Corporation | Enhancing toughness in microencapsulated nuclear fuel |
| CN113295577B (en) * | 2021-05-25 | 2022-04-15 | 中国核动力研究设计院 | Apparent density determination method for loose pyrolytic carbon layer of coated fuel particles |
-
1969
- 1969-03-31 CA CA047374A patent/CA918317A/en not_active Expired
- 1969-04-10 GB GB08344/69A patent/GB1206927A/en not_active Expired
- 1969-04-17 NL NL6905948A patent/NL6905948A/xx unknown
- 1969-04-22 DE DE19691920387 patent/DE1920387A1/en active Pending
- 1969-04-23 SE SE5779/69A patent/SE343163B/xx unknown
- 1969-04-23 BE BE731955D patent/BE731955A/xx unknown
- 1969-04-24 AT AT399169A patent/AT330906B/en not_active IP Right Cessation
- 1969-04-24 FR FR6912957A patent/FR2006915A1/en active Granted
- 1969-04-25 CH CH632469A patent/CH498470A/en not_active IP Right Cessation
Also Published As
| Publication number | Publication date |
|---|---|
| FR2006915A1 (en) | 1970-01-02 |
| SE343163B (en) | 1972-02-28 |
| DE1920387A1 (en) | 1970-01-02 |
| AT330906B (en) | 1976-07-26 |
| CH498470A (en) | 1970-10-31 |
| BE731955A (en) | 1969-10-01 |
| CA918317A (en) | 1973-01-02 |
| FR2006915B1 (en) | 1973-10-19 |
| NL6905948A (en) | 1969-10-28 |
| ATA399169A (en) | 1975-10-15 |
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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 |