GB1384049A - Nuclear reactors - Google Patents
Nuclear reactorsInfo
- Publication number
- GB1384049A GB1384049A GB180771A GB180771A GB1384049A GB 1384049 A GB1384049 A GB 1384049A GB 180771 A GB180771 A GB 180771A GB 180771 A GB180771 A GB 180771A GB 1384049 A GB1384049 A GB 1384049A
- Authority
- GB
- United Kingdom
- Prior art keywords
- helium
- boiler
- purifier
- pipe
- core chamber
- 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
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
- G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
- G21C19/303—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for gases
-
- 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
1384049 Nuclear reactors BRITISH NUCLEAR DESIGN & CONSTRUCTION Ltd 22 March 1972 [14 Jan 1971] 1807/71 Heading G6C In a helium-cooled nuclear reactor, a helium purification system is mounted within the concrete pressure vessel wall thickness, adjacent to the boiler system. The purifier 20, is mounted within the pad 14, together with the boiler 16, and circulator 18. Heated helium is drawn through passage 13 from the core chamber 12, and is urged downwardly through boiler 16 and upwardly through the annulus 36, to the core chamber inlet 15. A proportion of the helium, at 30, flows through pipe 28 into purifier 20 and emerges at the low pressure zone 32. Helium sampling is effected through the pipe 34.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB180771A GB1384049A (en) | 1971-01-14 | 1971-01-14 | Nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB180771A GB1384049A (en) | 1971-01-14 | 1971-01-14 | Nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1384049A true GB1384049A (en) | 1975-02-19 |
Family
ID=9728364
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB180771A Expired GB1384049A (en) | 1971-01-14 | 1971-01-14 | Nuclear reactors |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1384049A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109671509A (en) * | 2017-10-17 | 2019-04-23 | 华能山东石岛湾核电有限公司 | A kind of driving mechanism for control rod of high-temperature gas-cooled apparatus for examination and repair and maintenance craft method |
-
1971
- 1971-01-14 GB GB180771A patent/GB1384049A/en not_active Expired
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109671509A (en) * | 2017-10-17 | 2019-04-23 | 华能山东石岛湾核电有限公司 | A kind of driving mechanism for control rod of high-temperature gas-cooled apparatus for examination and repair and maintenance craft method |
CN109671509B (en) * | 2017-10-17 | 2024-04-09 | 华能山东石岛湾核电有限公司 | Overhauling device and overhauling process method for control rod driving mechanism of high-temperature gas cooled reactor |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PLNP | Patent lapsed through nonpayment of renewal fees |