GB1086052A - Improvements relating to nuclear reactor pipe coupling means - Google Patents
Improvements relating to nuclear reactor pipe coupling meansInfo
- Publication number
- GB1086052A GB1086052A GB18693/63A GB1869363A GB1086052A GB 1086052 A GB1086052 A GB 1086052A GB 18693/63 A GB18693/63 A GB 18693/63A GB 1869363 A GB1869363 A GB 1869363A GB 1086052 A GB1086052 A GB 1086052A
- Authority
- GB
- United Kingdom
- Prior art keywords
- region
- gas
- nuclear
- nuclear reactor
- passage
- 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
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/032—Joints between tubes and vessel walls, e.g. taking into account thermal stresses
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/30—Subcritical reactors ; Experimental reactors other than swimming-pool reactors or zero-energy reactors
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/22—Structural association of coolant tubes with headers
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1,086,052. Reactors. FAIREY ENGINEERING Ltd. Aug. 7, 1964 [May 10, 1963], No. 18693/63. Heading G6C. [Also in Division F2] In a gas-cooled, graphite-moderated experimental nuclear reactor of the zero-energy type the core 10 is constructed in two separate parts, i.e. an outer annular driver region 12 which runs at a low temperature in the region of 60‹ C., and a separate annular test region 13 of octagonal form and maintained by means of a flow of CO 2 cooling gas at any required temperature up to or exceeding 450‹ C. The region 13 comprises a stack of shaped graphite blocks formed with longitudinal channels through which the cooling gas is passed and with longitudinal channels which receive nuclear fuel and control rods. A thermal barrier 14 separates the regions 12 and 13 and the whole region 13 is removable for the purpose of changing its fuel pattern. The region 13 is formed with a vertical cylindrical open-ended void passage 15 to receive an interchangeable void tube 16 which defines a passage 17 in which a sample supported by a cable can be oscillated vertically in the nuclear flux at a varying frequency. The hot carbon-dioxide gas is supplied through ducts 18 which extend through the pressure shell cover 19 and which are thermally insulated by lagging boxes 20; the gas passes upwardly and is discharged laterally through a pipe 24 to the exterior of the pressure shell 11. Gamma radiation shielding 25, 26 and 27 encloses the top of the reactor core.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB18693/63A GB1086052A (en) | 1963-05-10 | 1963-05-10 | Improvements relating to nuclear reactor pipe coupling means |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB18693/63A GB1086052A (en) | 1963-05-10 | 1963-05-10 | Improvements relating to nuclear reactor pipe coupling means |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1086052A true GB1086052A (en) | 1967-10-04 |
Family
ID=10116802
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB18693/63A Expired GB1086052A (en) | 1963-05-10 | 1963-05-10 | Improvements relating to nuclear reactor pipe coupling means |
Country Status (1)
Country | Link |
---|---|
GB (1) | GB1086052A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0095662A1 (en) * | 1982-06-01 | 1983-12-07 | INTERATOM Gesellschaft mit beschränkter Haftung | High-temperature nuclear reactor wherein the hot gas conduit is disconnectable from the reactor vessel |
CN115862902A (en) * | 2022-09-22 | 2023-03-28 | 中国原子能科学研究院 | Reactor with a reactor core |
-
1963
- 1963-05-10 GB GB18693/63A patent/GB1086052A/en not_active Expired
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0095662A1 (en) * | 1982-06-01 | 1983-12-07 | INTERATOM Gesellschaft mit beschränkter Haftung | High-temperature nuclear reactor wherein the hot gas conduit is disconnectable from the reactor vessel |
CN115862902A (en) * | 2022-09-22 | 2023-03-28 | 中国原子能科学研究院 | Reactor with a reactor core |
CN115862902B (en) * | 2022-09-22 | 2024-05-14 | 中国原子能科学研究院 | Reactor with a reactor body |
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