GB2117169A - Double-wall tube with tritium barrier - Google Patents

Double-wall tube with tritium barrier Download PDF

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Publication number
GB2117169A
GB2117169A GB08230499A GB8230499A GB2117169A GB 2117169 A GB2117169 A GB 2117169A GB 08230499 A GB08230499 A GB 08230499A GB 8230499 A GB8230499 A GB 8230499A GB 2117169 A GB2117169 A GB 2117169A
Authority
GB
United Kingdom
Prior art keywords
tritium
interface
double wall
tubular wall
grooves
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.)
Granted
Application number
GB08230499A
Other versions
GB2117169B (en
Inventor
Larry Edward Efferding
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
CBS Corp
Original Assignee
Westinghouse Electric Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Publication of GB2117169A publication Critical patent/GB2117169A/en
Application granted granted Critical
Publication of GB2117169B publication Critical patent/GB2117169B/en
Expired legal-status Critical Current

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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)
  • Metallurgy (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

A double wall tube (1) for a liquid metal to water or steam heat exchanger, consisting of two concentric tubes 3, 5 with an oxide film on at least one tube surface wall at the interface of the concentric tubes (3, 5). Axial grooves (11) are formed in the tubes for collecting tritium and purging with inert gas to prevent the diffusion of tritium through the double wall tube (1). <IMAGE>

Description

SPECIFICATION Double-wall tube with tritium barrier This invention relates to steam generators for liquid metal nuclear reactors and more particularly to steam generated double wall tubes with a tritium barrier at the interface of the double wall.
Nuclear high temperature breeder reactors utilize a liquid metal as a coolant. They produce tritium in environmentally harmful qualities. Tritium, an isotope of hydrogen, readily diffuses through metal containers at the high reactor operating temperature. Thus it becomes necessary to provide a barrier to prevent the escape of the tritium. It is the principal object of the present invention to provide a tritium barrier and an arrangement which insures the integrity of the barrier so that the release of tritium from the equipment may be maintained at a safe level.
With this object in view, the present invention resides in a double wall tube for a steam generator utilized with a liquid metal cooled nuclear reactor, said double wall tube (1) comprising an outer tubular wall member (3) and an inner tubular wall member (5), with the grooves (11) disposed in one of the tubular wall members (3,5) at the interface of said tubular wall members (3,5), characterized in that at least one of said tubular wall members (3,5) is coated with an oxide film (7,9) on the interface surface so as to reduce its permeability for tritium.
One of the tubular wall members may have grooves at the interface of the tubular walls for collection and removal of tritium diffused into the interface area.
The invention will become more readily apparent from the following description of a preferred embodiment thereof shown by way of example only, in the accompanying drawing, in which: The sole figure is a sectional view of a double wall tube with an oxide coating on the interface surfaces of the tube an an inert gas purging system for grooves disposed at the interface of the tubular wall portions.
Referring now to the drawing in detail there is shown a double wall tube 1 for a steam generator utilized with a nuclear reactor cooled by a liquid metal. The double wall tube 1 comprises an outer tubular wall member 3 and an inner tubular wall member 5. Each tubular wall member 3, 5 has a film 7, 9, respectively, of magnetite, ferric oxide, Fe3O4, approximately 0.005 mm thick on the interface surfaces.
Grooves 11 are disposed in one of the tubular members, 5 as shown in the drawing, at the interface and extend lengthwise along the entire length of the tubular member 5.
The films 7 and 9 each reduce the diffusion of tritium by more than two orders of magnitude so that the combination of the two films reduce the diffusion of tritium through the double wall tube by more than four orders of magnitude that is to 10-4. The oxide films on both interface surfaces reduce the overall heat transfer producing a penalty of up to 15%; however, the reduction of tritium diffusion through the double wall tubes may simply be necessary.
While oxide films will build up on the inside of the inner tubular wall member 5 such films are not stable because of temperature shock and the presence of steam inherent in the operation of the steam generator. If the film at the interface is protected by inert gas, the oxide film at the interface surfaces are stabile.
Also shown is a sparging system for removing tritium from the grooves 11 at the interface of the tubular wall portions 3 and 5 by purging the grooves 11 with inert gas preferably helium. The purge rate is controlled by a controller 15, which measures the amount of tritium in the inert gas drawn from the grooves 11 and regulates the amount of inert gas vented through a tritium removal filter 1 7. The controller 1 5 also regulates a vent valve 19 and a supply valve 21 to control the purging of the grooves 11. The system could be a closed system utilizing a circulating pump and a tritium filter. A control supply valve would control the makeup to the system.
If the liquid metal is lithium, the outer tubular wall portion 3 is preferably made of a steel containing 2T% chromium and 1% molybdenum, which has high corrosion resistance in a liquid lithium environment.
The double wall tube 1 and inert gas monitoring and purging system hereinbefore described advantageously reduces the diffusion of tritium through the double wall tube 1 by several orders of magnitude and provides a check on the integrity of the tritium barrier.
Claims
1. A double wall tube for a steam generator utilized with a liquid metal cooled nuclear reactor, said double wall tube (1) comprising an outer tubular wall member (3) and an inner tubular wall member (5), with grooves (11) disposed in one of the tubular wall members (3,5) at the interface of said tubular wall members (3,5), characterized in that at least one of said tubular wall members (3,5) is coated with an oxide film (7,9) on the interface surface, so as to reduce its permeability for tritium.
2. A double wall tube as claimed in claim 1, characterized in that the oxide coating (7,9) consists of magnetite.
3. A double wall tube as claimed in claim 2, characterized in that the thickness of the coating (7,9) is approximately 0.005 mm.
4. A double wall tube as claimed in claim 1, 2 or 3, characterized in that the interface surface of each of said tubular members (3,5) is coated with an oxide film (7,9).
5. A double wall tube as set forth in any of claims 1 to 4, wherein a supply of inert gas and a
**WARNING** end of DESC field may overlap start of CLMS **.

Claims (5)

**WARNING** start of CLMS field may overlap end of DESC **. SPECIFICATION Double-wall tube with tritium barrier This invention relates to steam generators for liquid metal nuclear reactors and more particularly to steam generated double wall tubes with a tritium barrier at the interface of the double wall. Nuclear high temperature breeder reactors utilize a liquid metal as a coolant. They produce tritium in environmentally harmful qualities. Tritium, an isotope of hydrogen, readily diffuses through metal containers at the high reactor operating temperature. Thus it becomes necessary to provide a barrier to prevent the escape of the tritium. It is the principal object of the present invention to provide a tritium barrier and an arrangement which insures the integrity of the barrier so that the release of tritium from the equipment may be maintained at a safe level. With this object in view, the present invention resides in a double wall tube for a steam generator utilized with a liquid metal cooled nuclear reactor, said double wall tube (1) comprising an outer tubular wall member (3) and an inner tubular wall member (5), with the grooves (11) disposed in one of the tubular wall members (3,5) at the interface of said tubular wall members (3,5), characterized in that at least one of said tubular wall members (3,5) is coated with an oxide film (7,9) on the interface surface so as to reduce its permeability for tritium. One of the tubular wall members may have grooves at the interface of the tubular walls for collection and removal of tritium diffused into the interface area. The invention will become more readily apparent from the following description of a preferred embodiment thereof shown by way of example only, in the accompanying drawing, in which: The sole figure is a sectional view of a double wall tube with an oxide coating on the interface surfaces of the tube an an inert gas purging system for grooves disposed at the interface of the tubular wall portions. Referring now to the drawing in detail there is shown a double wall tube 1 for a steam generator utilized with a nuclear reactor cooled by a liquid metal. The double wall tube 1 comprises an outer tubular wall member 3 and an inner tubular wall member 5. Each tubular wall member 3, 5 has a film 7, 9, respectively, of magnetite, ferric oxide, Fe3O4, approximately 0.005 mm thick on the interface surfaces. Grooves 11 are disposed in one of the tubular members, 5 as shown in the drawing, at the interface and extend lengthwise along the entire length of the tubular member 5. The films 7 and 9 each reduce the diffusion of tritium by more than two orders of magnitude so that the combination of the two films reduce the diffusion of tritium through the double wall tube by more than four orders of magnitude that is to 10-4. The oxide films on both interface surfaces reduce the overall heat transfer producing a penalty of up to 15%; however, the reduction of tritium diffusion through the double wall tubes may simply be necessary. While oxide films will build up on the inside of the inner tubular wall member 5 such films are not stable because of temperature shock and the presence of steam inherent in the operation of the steam generator. If the film at the interface is protected by inert gas, the oxide film at the interface surfaces are stabile. Also shown is a sparging system for removing tritium from the grooves 11 at the interface of the tubular wall portions 3 and 5 by purging the grooves 11 with inert gas preferably helium. The purge rate is controlled by a controller 15, which measures the amount of tritium in the inert gas drawn from the grooves 11 and regulates the amount of inert gas vented through a tritium removal filter 1 7. The controller 1 5 also regulates a vent valve 19 and a supply valve 21 to control the purging of the grooves 11. The system could be a closed system utilizing a circulating pump and a tritium filter. A control supply valve would control the makeup to the system. If the liquid metal is lithium, the outer tubular wall portion 3 is preferably made of a steel containing 2T% chromium and 1% molybdenum, which has high corrosion resistance in a liquid lithium environment. The double wall tube 1 and inert gas monitoring and purging system hereinbefore described advantageously reduces the diffusion of tritium through the double wall tube 1 by several orders of magnitude and provides a check on the integrity of the tritium barrier. Claims
1. A double wall tube for a steam generator utilized with a liquid metal cooled nuclear reactor, said double wall tube (1) comprising an outer tubular wall member (3) and an inner tubular wall member (5), with grooves (11) disposed in one of the tubular wall members (3,5) at the interface of said tubular wall members (3,5), characterized in that at least one of said tubular wall members (3,5) is coated with an oxide film (7,9) on the interface surface, so as to reduce its permeability for tritium.
2. A double wall tube as claimed in claim 1, characterized in that the oxide coating (7,9) consists of magnetite.
3. A double wall tube as claimed in claim 2, characterized in that the thickness of the coating (7,9) is approximately 0.005 mm.
4. A double wall tube as claimed in claim 1, 2 or 3, characterized in that the interface surface of each of said tubular members (3,5) is coated with an oxide film (7,9).
5. A double wall tube as set forth in any of claims 1 to 4, wherein a supply of inert gas and a tritium monitor ( 15) are associated therewith, characterized by controlling means for providing an inert gas flow through the grooves (11), and means for monitoring the amount of tritium in the inert gas discharged from said grooves to determine the integrity of the coatings (7,9).
GB08230499A 1982-03-16 1982-10-26 Double-wall tube with tritium barrier Expired GB2117169B (en)

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 true GB2117169A (en) 1983-10-05
GB2117169B 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)

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JP (1) JPS58158401A (en)
FR (1) FR2523756B1 (en)
GB (1) GB2117169B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2583865A1 (en) * 1985-06-19 1986-12-26 Commissariat Energie Atomique COAXIAL U TUBE HEAT EXCHANGER WITH NEUTRAL GAS INTERMEDIATE FLOW AND NUCLEAR FAST NEUTRON REACTOR COMPRISING EXCHANGERS OF THIS TYPE.
EP0367584A2 (en) * 1988-11-02 1990-05-09 Atomic Energy Of Canada Limited -Energie Atomique Du Canada Limitee Pressure vessel

Family Cites Families (2)

* Cited by examiner, † Cited by third party
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

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2583865A1 (en) * 1985-06-19 1986-12-26 Commissariat Energie Atomique COAXIAL U TUBE HEAT EXCHANGER WITH NEUTRAL GAS INTERMEDIATE FLOW AND NUCLEAR FAST NEUTRON REACTOR COMPRISING EXCHANGERS OF THIS TYPE.
EP0206921A1 (en) * 1985-06-19 1986-12-30 Commissariat A L'energie Atomique Heat exchanger with coaxial U-tubes and intermediate circulation of neutral gas, and fast neutron reactor comprising such a heat exchanger
EP0367584A2 (en) * 1988-11-02 1990-05-09 Atomic Energy Of Canada Limited -Energie Atomique Du Canada Limitee Pressure vessel
EP0367584A3 (en) * 1988-11-02 1990-08-22 Atomic Energy Of Canada Limited -Energie Atomique Du Canada Limitee Pressure vessel

Also Published As

Publication number Publication date
GB2117169B (en) 1985-07-31
JPS58158401A (en) 1983-09-20
FR2523756B1 (en) 1986-04-18
FR2523756A1 (en) 1983-09-23

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PCNP Patent ceased through non-payment of renewal fee