GB2117169B - Double-wall tube with tritium barrier - Google Patents
Double-wall tube with tritium barrierInfo
- Publication number
- GB2117169B GB2117169B GB08230499A GB8230499A GB2117169B GB 2117169 B GB2117169 B GB 2117169B GB 08230499 A GB08230499 A GB 08230499A GB 8230499 A GB8230499 A GB 8230499A GB 2117169 B GB2117169 B GB 2117169B
- Authority
- GB
- United Kingdom
- Prior art keywords
- double
- wall tube
- tritium
- barrier
- tritium barrier
- 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
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F28—HEAT EXCHANGE IN GENERAL
- F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
- F28F1/00—Tubular elements; Assemblies of tubular elements
- F28F1/003—Multiple wall conduits, e.g. for leak detection
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/06—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium
- F22B1/063—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium for metal cooled nuclear reactors
- F22B1/066—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being molten; Use of molten metal, e.g. zinc, as heat transfer medium for metal cooled nuclear reactors with double-wall tubes having a third fluid between these walls, e.g. helium for leak detection
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/04—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler and characterised by material, e.g. use of special steel alloy
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/10—Water tubes; Accessories therefor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/10—Means for preventing contamination in the event of leakage, e.g. double wall
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Sustainable Development (AREA)
- Sustainable Energy (AREA)
- Life Sciences & Earth Sciences (AREA)
- Metallurgy (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US35872182A | 1982-03-16 | 1982-03-16 |
Publications (2)
Publication Number | Publication Date |
---|---|
GB2117169A GB2117169A (en) | 1983-10-05 |
GB2117169B true GB2117169B (en) | 1985-07-31 |
Family
ID=23410759
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB08230499A Expired GB2117169B (en) | 1982-03-16 | 1982-10-26 | Double-wall tube with tritium barrier |
Country Status (3)
Country | Link |
---|---|
JP (1) | JPS58158401A (en) |
FR (1) | FR2523756B1 (en) |
GB (1) | GB2117169B (en) |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2583865B1 (en) * | 1985-06-19 | 1989-03-31 | Commissariat Energie Atomique | COAXIAL U TUBE HEAT EXCHANGER WITH NEUTRAL GAS INTERMEDIATE FLOW AND NUCLEAR FAST NEUTRON REACTOR COMPRISING EXCHANGERS OF THIS TYPE. |
US4986112A (en) * | 1988-11-02 | 1991-01-22 | Atomic Energy Of Canada Ltd. | Composite pressure vessel for a nuclear environment |
CN112871577A (en) * | 2019-11-29 | 2021-06-01 | 核工业西南物理研究院 | Preparation method of pipe fitting inner and outer wall heterogeneous tritium-resistant coating and film forming device |
Family Cites Families (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2318556A1 (en) * | 1973-04-12 | 1974-10-31 | Kraftwerk Union Ag | Magnetite corrosion proofing layer - in steam power plant, formed by passing steam through plant before use |
DE2703975C3 (en) * | 1977-02-01 | 1981-10-15 | Kernforschungsanlage Jülich GmbH, 5170 Jülich | Tritium permeation barrier for highly heat-resistant materials |
-
1982
- 1982-10-26 GB GB08230499A patent/GB2117169B/en not_active Expired
- 1982-11-15 FR FR8219088A patent/FR2523756B1/en not_active Expired
- 1982-11-16 JP JP57199858A patent/JPS58158401A/en active Pending
Also Published As
Publication number | Publication date |
---|---|
FR2523756B1 (en) | 1986-04-18 |
JPS58158401A (en) | 1983-09-20 |
FR2523756A1 (en) | 1983-09-23 |
GB2117169A (en) | 1983-10-05 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PCNP | Patent ceased through non-payment of renewal fee |