GB1465630A - Nuclear reactor fuel elements and their manufacture - Google Patents
Nuclear reactor fuel elements and their manufactureInfo
- Publication number
- GB1465630A GB1465630A GB1912074A GB1912074A GB1465630A GB 1465630 A GB1465630 A GB 1465630A GB 1912074 A GB1912074 A GB 1912074A GB 1912074 A GB1912074 A GB 1912074A GB 1465630 A GB1465630 A GB 1465630A
- Authority
- GB
- United Kingdom
- Prior art keywords
- container
- getter material
- getter
- fuel
- fuel element
- 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
- 238000004519 manufacturing process Methods 0.000 title abstract 2
- 239000003758 nuclear fuel Substances 0.000 title 1
- 239000000463 material Substances 0.000 abstract 9
- 239000000446 fuel Substances 0.000 abstract 8
- 229910052751 metal Inorganic materials 0.000 abstract 5
- 239000002184 metal Substances 0.000 abstract 5
- 239000007789 gas Substances 0.000 abstract 3
- 239000011521 glass Substances 0.000 abstract 3
- 229910000986 non-evaporable getter Inorganic materials 0.000 abstract 3
- 239000011888 foil Substances 0.000 abstract 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 abstract 1
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 abstract 1
- 101100533558 Mus musculus Sipa1 gene Proteins 0.000 abstract 1
- 238000007511 glassblowing Methods 0.000 abstract 1
- 229910002804 graphite Inorganic materials 0.000 abstract 1
- 239000010439 graphite Substances 0.000 abstract 1
- 239000011261 inert gas Substances 0.000 abstract 1
- 238000000034 method Methods 0.000 abstract 1
- 229910052750 molybdenum Inorganic materials 0.000 abstract 1
- 239000011733 molybdenum Substances 0.000 abstract 1
- 239000008188 pellet Substances 0.000 abstract 1
- 238000005086 pumping Methods 0.000 abstract 1
- 238000001275 scanning Auger electron spectroscopy Methods 0.000 abstract 1
- 238000009834 vaporization Methods 0.000 abstract 1
- 230000008016 vaporization Effects 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
- G21C3/16—Details of the construction within the casing
- G21C3/17—Means for storage or immobilisation of gases in 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)
- Compressors, Vaccum Pumps And Other Relevant Systems (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
Abstract
1465630 Fuel elements SAES GETTERS SpA 1 May 1974 [2 May 1973] 19120/74 Heading G6C A fuel element contains a non-evaporable getter material which, as the temperature of the fuel element is increased, starts to sorb active gases at a temperature lower than that at which the fuel element walls start to do so, and at a rate such as to prevent the said walls sorbing any appreciable amount of said gases, the said getter material having a sorptive capacity of at least 5 c.c.-torr./g. of CO at 20 C. By "non- evaporable getter material" is meant one which acts as a getter below its vaporization temperature. The fuel element (Fig. 1, not shown), comprises a hermetically sealed metallic container having walls forming a fuel-containing chamber and a plenum chamber. The getter device is placed within the plenum chamber, being separated from the end closure member by a helical spring and from the fuel by a ZrO 2 insulating pellet. Suitable getter materials are those described in Specification 1,463,538). The getter material may be housed in a container of e.g. molybdenum or graphite (Fig. 2, not shown), or be surrounded by one or more metal support rings (Fig. 5, not shown). In a further embodiment, shown in Fig. 3, a getter device 30 comprises an activated non-evaporable getter material 31 held within a metal container 32 by springs 33, 33<SP>1</SP>. One end of the container 32 is sealed by a thin metal foil 36 welded at 53 and having score lines defining an area of structural weakness which can be preferentially ruptured. The container interior 37 is either evacuated or filled with an inert gas, e.g. He at slightly above atmospheric pressure via a metal pumping stem 38 which can be pinched-off. During its manufacture, the fuel element is filled with He to 20 atmospheres pressure whereupon the foil 36 is ruptured and the getter material 31 exposed to the gases in the plenum chamber. In a still further embodiment, shown in Fig. 4, getter material 41 is held within a glass container 42 by springs 43, 43<SP>1</SP>. End 44 of container 42 is sealed by normal glass blowing techniques while the other end is a dome 45 of prestressed glass. The glass container 42 is placed within a metal holder 46 terminating at the end adjacent dome 45 in a wire mesh 47. The filling with He in this case causes the dome 45 to break into a large number of small pieces thus ensuring complete contact of the getter material 41 with the plenum chamber atmosphere.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
IT23613/73A IT992548B (en) | 1973-05-02 | 1973-05-02 | NUCLEA RE FUEL ELEMENTS AND THEIR MANUFACTURING METHOD |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1465630A true GB1465630A (en) | 1977-02-23 |
Family
ID=11208575
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB1912074A Expired GB1465630A (en) | 1973-05-02 | 1974-05-01 | Nuclear reactor fuel elements and their manufacture |
Country Status (8)
Country | Link |
---|---|
JP (1) | JPS5048394A (en) |
CA (1) | CA1017469A (en) |
DE (1) | DE2421295A1 (en) |
FR (1) | FR2228274B3 (en) |
GB (1) | GB1465630A (en) |
IT (1) | IT992548B (en) |
NL (1) | NL7405896A (en) |
SE (1) | SE413711B (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4279700A (en) | 1976-11-15 | 1981-07-21 | Westinghouse Electric Corp. | Tritium removal and retention device |
-
1973
- 1973-05-02 IT IT23613/73A patent/IT992548B/en active
-
1974
- 1974-04-30 SE SE7405807A patent/SE413711B/en unknown
- 1974-04-30 FR FR7415120A patent/FR2228274B3/fr not_active Expired
- 1974-05-01 GB GB1912074A patent/GB1465630A/en not_active Expired
- 1974-05-02 NL NL7405896A patent/NL7405896A/xx not_active Application Discontinuation
- 1974-05-02 DE DE2421295A patent/DE2421295A1/en not_active Withdrawn
- 1974-05-02 JP JP49048848A patent/JPS5048394A/ja active Pending
- 1974-05-13 CA CA199,644A patent/CA1017469A/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
DE2421295A1 (en) | 1974-11-14 |
JPS5048394A (en) | 1975-04-30 |
FR2228274A1 (en) | 1974-11-29 |
NL7405896A (en) | 1974-11-05 |
SE413711B (en) | 1980-06-16 |
IT992548B (en) | 1975-09-30 |
CA1017469A (en) | 1977-09-13 |
FR2228274B3 (en) | 1977-03-04 |
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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 |