GB1271574A - Improvements in and relating to nuclear fuel elements - Google Patents
Improvements in and relating to nuclear fuel elementsInfo
- Publication number
- GB1271574A GB1271574A GB36342/69A GB3634269A GB1271574A GB 1271574 A GB1271574 A GB 1271574A GB 36342/69 A GB36342/69 A GB 36342/69A GB 3634269 A GB3634269 A GB 3634269A GB 1271574 A GB1271574 A GB 1271574A
- Authority
- GB
- United Kingdom
- Prior art keywords
- tube
- chamber
- fission
- cladding
- orifices
- 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
- 230000004992 fission Effects 0.000 abstract 6
- 239000000446 fuel Substances 0.000 abstract 4
- 239000007789 gas Substances 0.000 abstract 4
- 238000005253 cladding Methods 0.000 abstract 3
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 abstract 1
- 230000005494 condensation Effects 0.000 abstract 1
- 238000009833 condensation Methods 0.000 abstract 1
- 239000002826 coolant Substances 0.000 abstract 1
- 239000007788 liquid Substances 0.000 abstract 1
- 229910052751 metal Inorganic materials 0.000 abstract 1
- 239000002184 metal Substances 0.000 abstract 1
- 239000008188 pellet Substances 0.000 abstract 1
- 239000011148 porous material Substances 0.000 abstract 1
- 229910052708 sodium Inorganic materials 0.000 abstract 1
- 239000011734 sodium Substances 0.000 abstract 1
- 239000010935 stainless steel Substances 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
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/041—Means for removal of gases from fuel elements
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
1,271,574. Fuel elements. COMMISSARIAT A L'ENERGIE ATOMIQUE. 18 July, 1969 [23 July, 1968], No. 36342/69. Heading G6C. A fuel element has a vent in the form of a tube providing a restricted passage for the removal of fission gas, the tube being disposed and terminating at one end in a chamber which will surmount the portion of the cladding which will be uppermost when the fuel element is in its operative position, the chamber having in its portion which will be lowermost discharge orifices for fission gases leaving the element. In the embodiment shown, the vent is a filled tube 10 housed within an upper chamber 6 of the element, being wound helically on itself with its lower end 13 passing through a plate 4 which separates the chamber 6 from an intermediate chamber 7 housing a stack of fuel pellets 9. The tube 10 is formed of corrosion-resistant steel and is filled with a compact but porous material, preferably MgO. On leaving the tube 10, the fission gases escape through orifices 14 near the bottom of the chamber 6. The tube 10 produces a considerable head loss during passage of the fission gases and consequently the pressure within the cladding 1 is greater than that of the external medium, e.g. liquid sodium coolant. As a result, the medium does not enter the cladding through the orifices 14. A filter 15, e.g. a sintered metal disc, protects the end 13 of the tube 10 from deposits and the condensation of certain fission products, e.g. Cs. A chamber 8 in the lower portion of the element, i.e. its coolest region, traps condensable fission products, e.g. Cs, Rb and Te. In place of the filled tube 10, a crushed or extruded capillary tube may be used.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR160313 | 1968-07-23 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1271574A true GB1271574A (en) | 1972-04-19 |
Family
ID=8652959
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB36342/69A Expired GB1271574A (en) | 1968-07-23 | 1969-07-18 | Improvements in and relating to nuclear fuel elements |
Country Status (4)
| Country | Link |
|---|---|
| BE (1) | BE735474A (en) |
| DE (1) | DE6928753U (en) |
| FR (1) | FR1596521A (en) |
| GB (1) | GB1271574A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP2236860A2 (en) | 2009-04-03 | 2010-10-06 | Franz Ackerl | Mechanical slip limiter |
-
1968
- 1968-07-23 FR FR160313A patent/FR1596521A/fr not_active Expired
-
1969
- 1969-07-01 BE BE735474D patent/BE735474A/xx unknown
- 1969-07-18 GB GB36342/69A patent/GB1271574A/en not_active Expired
- 1969-07-21 DE DE6928753U patent/DE6928753U/en not_active Expired
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP2236860A2 (en) | 2009-04-03 | 2010-10-06 | Franz Ackerl | Mechanical slip limiter |
Also Published As
| Publication number | Publication date |
|---|---|
| DE6928753U (en) | 1970-02-05 |
| FR1596521A (en) | 1970-06-22 |
| BE735474A (en) | 1969-12-16 |
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