GB1025859A - Base support grid for nuclear reactors - Google Patents

Base support grid for nuclear reactors

Info

Publication number
GB1025859A
GB1025859A GB10385/63D GB1038563D GB1025859A GB 1025859 A GB1025859 A GB 1025859A GB 10385/63 D GB10385/63 D GB 10385/63D GB 1038563 D GB1038563 D GB 1038563D GB 1025859 A GB1025859 A GB 1025859A
Authority
GB
United Kingdom
Prior art keywords
plate
rods
graphite
grid
temperature
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
Application number
GB10385/63D
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Publication of GB1025859A publication Critical patent/GB1025859A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/32Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/32Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
    • G21C1/324Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed beneath the core
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/02Details
    • G21C13/04Arrangements for expansion and contraction
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02Details
    • G21C5/10Means for supporting the complete structure
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

1,025,859. Reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. March 11, 1965 [March 11, 1964], No. 10385/65. Heading G6C. A base support grid for a gas-cooled nuclear reactor comprises a plate made up of at least one layer of connected blocks of a refractory material, e.g. graphite, supporting the reactor core and pierced by channels for the passage of the cooling gas, together with means for imposing sufficient prestressed radial pressure on the plate to prevent the development of tensile stress within the plate. As shown in Fig. 1, an integral, high temperature, heliumcooled nuclear reactor incorporating the above grid comprises an envelope A serving both as pressure vessel and as biological shield and consisting of a casing of prestressed concrete lined on the inside with a metallic shield 10. The reactor core B is supported by a base support grid C above heat exchangers D comprising six separate heat exchange loops 16. The circulation of the helium coolant is indicated by the arrows f, the helium at its lowest temperature starting from the top of the compartment 14 and passing down through the core B in which it becomes heated, then through the base support grid C and the heat exchangers D, returning through an annular compartment 24 between partitions 20 and the inner side wall of the envelope A. Blowers 22 connected one to each heat exchange loop 16 (only one of which is shown) force the helium round the circuit. The core B comprises an active central region 26 made up of one or several layers of fuel assemblies of hexagonal cross-section, each composed of fissile particles coated in pyrolytic graphite and dispersed in a graphite matrix pierced with a longitudinal channel for the helium to pass through. Surrounding the active region 26 of the core is a reflector 27 composed of moderator rods of similar shape to the fuel assemblies. The helium enters the core B at a temperature of about 300‹C. and leaves at a temperature of about 750‹ C. The central part of the plate 34, which has to be capable of withstanding this high outlet temperature, is composed of one or several layers of graphite rods of the same cross-section as the fuel assemblies and each pierced by an axial channel to allow passage of the helium, cotter pins being arranged between the rods in order to supplement the frictional forces between the rods and to avoid any displacement of the rods, in particular during rises in temperature. The graphite may include absorptive material such as boron in order to act as a biological shield for the heat exchangers D. Alternatively, alternate layers of graphite and of a graphite-boron mixture, the latter being of a very low order of thickness, may be used. The temperature is uniform throughout the central part of the grid with the result that there is a temperature drop of about 450‹ C. across the outer part 38 of the plate 34 which supports the reflector 27. This outer part 38 is composed of graphite bars of trapezoidal cross-section, the parallel sides of which are orientated in the direction of circles centred on the axis of the grid, the other two sides being orientated in radial directions. These bars do not require such intense cooling as do the rods supporting the active region 26 of the core and longitudinal channels of smaller diameter than those through the active region 26 pierce both the rods of the reflector 27 and the corresponding bars of the grid. These latter have transverse ribs which interleave in such a way as to supplement the frictional forces between the bars. The plate 34 is encompassed by a series of brackets 58 which are linked to each other by means of flexible metallic membranes so as to maintain at least an approximation of gas tightness between the brackets 58. As shown in Fig. 4, flanges 62 at the bottom of the brackets 58 support the outermost bars of the plate 34. Each bracket 58 is linked by a traction strip 64 to a circular beam 66 for stress distribution which is suspended from the upper part of the envelope A by a series of tie-rods 68. The means for prestressing the plate 34 comprises a rigid girdle 70 and sets of elastic pressure members 72, one set associated with each bracket 58 and compressed between the bracket 58 and a bearing plate 74, the distance of the latter from the girdle 70 being determined by an adjustable wedge device. This device comprises two wedges 76 integral with the bearing plate 74 and two wedges 78 which can be driven in to a greater or lesser extent between the wedges 76 and the girdle 70 (only one each of the wedges 76, 78 being seen in Fig. 4). Each of the members 72 contains a stack of Belleville washers or other type of spring. The application of the prestressing to the plate 34 is effected by first supporting the plate 34 and the girdle 70 by a temporary scaffolding and then placing two batteries of jacks, each battery applied to one bracket 58, adjacent radially opposite areas of the base support grid and putting the jacks under pressure in order to compress the members 72. Once the prestressing force is regulated, the wedges 78 are driven in and the jacks dismantled. The jacks are then placed in other positions around the grid and the same operation is repeated from place to place. Instead of being carried out in one single operation, the prestressing is achieved in successive tages as a result of a number of repeated adjustments to the same brackets 58.
GB10385/63D 1964-03-11 1965-03-11 Base support grid for nuclear reactors Expired GB1025859A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR966985A FR1396470A (en) 1964-03-11 1964-03-11 Support area for nuclear reactor

Publications (1)

Publication Number Publication Date
GB1025859A true GB1025859A (en) 1966-04-14

Family

ID=8825267

Family Applications (1)

Application Number Title Priority Date Filing Date
GB10385/63D Expired GB1025859A (en) 1964-03-11 1965-03-11 Base support grid for nuclear reactors

Country Status (4)

Country Link
AT (1) AT267005B (en)
CH (1) CH426029A (en)
FR (1) FR1396470A (en)
GB (1) GB1025859A (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3359175A (en) * 1966-09-16 1967-12-19 Ian P Arthur Nuclear reactor
FR2462000A1 (en) * 1979-07-23 1981-02-06 Hochtemperatur Reaktorbau Gmbh CARRIER BASE FORMED OF A LARGE NUMBER OF GRAPHITE BLOCKS FOR THE HEART OF A NUCLEAR REACTOR WITH SPHERICAL FUEL ELEMENTS
DE3141734A1 (en) * 1981-10-21 1983-04-28 Hochtemperatur-Reaktorbau GmbH, 5000 Köln Nuclear reactor having a gas-cooled pebble-bed nuclear reactor
US4474729A (en) * 1980-05-16 1984-10-02 Hochtemperatur-Reaktorbau Gmbh. Support structure for a prestressed cylindrical pressure vessel
US4698203A (en) * 1980-12-19 1987-10-06 Hochtemperatur-Reaktorbau Gmbh Gas-cooled nuclear reactor with a bed of spherical fuel elements

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114220569B (en) * 2021-11-11 2022-10-25 华能核能技术研究院有限公司 Compact ball bed high temperature gas cooled reactor primary loop device

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3359175A (en) * 1966-09-16 1967-12-19 Ian P Arthur Nuclear reactor
FR2462000A1 (en) * 1979-07-23 1981-02-06 Hochtemperatur Reaktorbau Gmbh CARRIER BASE FORMED OF A LARGE NUMBER OF GRAPHITE BLOCKS FOR THE HEART OF A NUCLEAR REACTOR WITH SPHERICAL FUEL ELEMENTS
US4474729A (en) * 1980-05-16 1984-10-02 Hochtemperatur-Reaktorbau Gmbh. Support structure for a prestressed cylindrical pressure vessel
US4698203A (en) * 1980-12-19 1987-10-06 Hochtemperatur-Reaktorbau Gmbh Gas-cooled nuclear reactor with a bed of spherical fuel elements
DE3141734A1 (en) * 1981-10-21 1983-04-28 Hochtemperatur-Reaktorbau GmbH, 5000 Köln Nuclear reactor having a gas-cooled pebble-bed nuclear reactor

Also Published As

Publication number Publication date
FR1396470A (en) 1965-04-23
AT267005B (en) 1968-12-10
CH426029A (en) 1966-12-15

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