GB1135396A - Improvements in or relating to fluid cooled nuclear reactors - Google Patents

Improvements in or relating to fluid cooled nuclear reactors

Info

Publication number
GB1135396A
GB1135396A GB33491/65A GB3349165A GB1135396A GB 1135396 A GB1135396 A GB 1135396A GB 33491/65 A GB33491/65 A GB 33491/65A GB 3349165 A GB3349165 A GB 3349165A GB 1135396 A GB1135396 A GB 1135396A
Authority
GB
United Kingdom
Prior art keywords
marbles
coolant
aggregation
reactor
diagrid
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
GB33491/65A
Inventor
Roger Thomas Galletly
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
Priority to GB33491/65A priority Critical patent/GB1135396A/en
Priority to DE1564986A priority patent/DE1564986C3/en
Publication of GB1135396A publication Critical patent/GB1135396A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/07Pebble-bed reactors; Reactors with granular fuel
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)

Abstract

1,135,396. Reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. 25 July, 1966 [5 Aug., 1965], No. 33491/65. Heading G6C. A downward coolant flow, pebble bed nuclear reactor has a fissile pebble bed supported by, but spaced above, a base-plate and a disposition of coolant outlet ducts such that a downward flow of coolant through the bed changes direction from vertically downward to transverse within the spacing between the pebble bed and the base-plate. In the embodiment described, the core aggregation 12 of a gas-cooled pebble bed reactor consists of graphite marbles 13 in which fissile fuel particles are embedded. Replacement marbles are added at the top of the reactor vessel 11 whilst irradiated marbles the withdrawn from underneath through a pipe 15 under the control of a valve 14. The core aggregation 12 is supported on a support aggregation 16 permeable to coolant and consisting of secondary graphite marbles 17 which also extend up the sides of the core aggregation 12 to serve both as a containment for the aggregation 12 and as a neutron reflector. The support aggregation 16 is carried upon a diagrid 18 peripherally supported by the reactor vessel 11. The permeability to the coolant of the support aggregation 16 is reduced except along a preferential path for the heated coolant from the core aggregation 12 by disposing small refractory marbles 20, either freely or spot welded, in the spaces between the secondary marbles 17. The coolant travels along this preferential path to outlets 19 in the reactor vessel 11 situated above the diagrid 18, the diagrid thus being shielded from exposure to the hot coolant. The secondary marbles 17 may be spot welded to each other, and possibly also to the small marbles 20, to give a rigid support aggregation. Also the marbles 17 may contain fertile material to provide a breeding reactor system, but in this case they would not be joined together so as to facilitate discharge for chemical extraction of the bred fuel.
GB33491/65A 1965-08-05 1965-08-05 Improvements in or relating to fluid cooled nuclear reactors Expired GB1135396A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB33491/65A GB1135396A (en) 1965-08-05 1965-08-05 Improvements in or relating to fluid cooled nuclear reactors
DE1564986A DE1564986C3 (en) 1965-08-05 1966-08-03 Nuclear reactor with a pile of heat-resistant, fissile core bodies

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB33491/65A GB1135396A (en) 1965-08-05 1965-08-05 Improvements in or relating to fluid cooled nuclear reactors

Publications (1)

Publication Number Publication Date
GB1135396A true GB1135396A (en) 1968-12-04

Family

ID=10353663

Family Applications (1)

Application Number Title Priority Date Filing Date
GB33491/65A Expired GB1135396A (en) 1965-08-05 1965-08-05 Improvements in or relating to fluid cooled nuclear reactors

Country Status (2)

Country Link
DE (1) DE1564986C3 (en)
GB (1) GB1135396A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2315748A1 (en) * 1975-06-26 1977-01-21 Electricite De France Moderator structure - for a molten fuel salt bore reactor, preferably with independent, stacked moderator modules
FR2402282A1 (en) * 1977-09-06 1979-03-30 Commissariat Energie Atomique Nuclear high temp. reactor - with movable graphite block for exchange of spent graphite reflector pebbles
US4183785A (en) * 1975-06-26 1980-01-15 Electricite de France (Service National) Pechiney Ugine-Kuhlmann Method for positioning moderator structure for the core of a molten-salt reactor
EP0081778A1 (en) * 1981-12-16 1983-06-22 Forschungszentrum Jülich Gmbh Pebble bed nuclear reactor with self regulation in an accidental situation

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2414757C2 (en) * 1974-03-27 1984-06-14 Interatom Internationale Atomreaktorbau Gmbh, 5060 Bergisch Gladbach Reflector cooling for pebble bed reactors
DE2738729C2 (en) * 1977-08-27 1985-07-25 Hochtemperatur-Reaktorbau GmbH, 4600 Dortmund Device for the construction of an edge zone from pure graphite spheres around the operating element bed of a high-temperature reactor

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2315748A1 (en) * 1975-06-26 1977-01-21 Electricite De France Moderator structure - for a molten fuel salt bore reactor, preferably with independent, stacked moderator modules
US4183785A (en) * 1975-06-26 1980-01-15 Electricite de France (Service National) Pechiney Ugine-Kuhlmann Method for positioning moderator structure for the core of a molten-salt reactor
FR2402282A1 (en) * 1977-09-06 1979-03-30 Commissariat Energie Atomique Nuclear high temp. reactor - with movable graphite block for exchange of spent graphite reflector pebbles
EP0081778A1 (en) * 1981-12-16 1983-06-22 Forschungszentrum Jülich Gmbh Pebble bed nuclear reactor with self regulation in an accidental situation

Also Published As

Publication number Publication date
DE1564986A1 (en) 1970-02-12
DE1564986C3 (en) 1975-06-26
DE1564986B2 (en) 1974-11-14

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