GB817754A - Nuclear reactor - Google Patents

Nuclear reactor

Info

Publication number
GB817754A
GB817754A GB5513/46A GB551346A GB817754A GB 817754 A GB817754 A GB 817754A GB 5513/46 A GB5513/46 A GB 5513/46A GB 551346 A GB551346 A GB 551346A GB 817754 A GB817754 A GB 817754A
Authority
GB
United Kingdom
Prior art keywords
reactor
fuel
graphite
shield
chamber
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
GB5513/46A
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 GB817754A publication Critical patent/GB817754A/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
    • G21C1/08Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/10Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
    • G21C1/12Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
    • 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

Abstract

817,754. Nuclear reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Feb. 21, 1946 [Feb. 16, 1945], No. 5513/46. Class 39(4). A nuclear reactor comprises bodies of fissile material geometrically arranged in a low neutron absorbing moderator material, means for passing a fluid in heat exchange relationship with the fissile material, and means for extracting heat from the fluid. Fig 2 shows a cross-section of a graphite moderated helium cooled reactor. The lower chamber 35 serves as a gas inlet and fuel element discharge chamber ; above this in the chamber 37 is the reactor core (not shown) comprising graphite bricks secured together by dowel pins and provided with vertical fuel channels, the lattice being surrounded on all sides and at the top and bottom by less pure graphite which acts as a reflector. Guide tubes 58 fit into the tops of the fuel channels and are provided with slots to allow the coolant gas to pass to the discharge nozzles 57. Above the outlet gas chamber is a neutron and gamma ray shield comprising a layer of steel plates 64 and a layer of graphite 62 supported on a steel floor 60 ; the guide tubes extend through the shield and are normally closed by removable shield plugs of steel and graphite, similar to the neutron and gamma ray shield. The dome 39 is provided with a manhole 73 to allow access for loading fuel elements into the reactor. Each row of fuel element columns is supported on two cans 59 provided with small apertures through which the helium coolant can pass and with large apertures through which the fuel elements can pass ; thus if the cans are moved to place their large apertures underneath the fuel channels, the row of fuel elements is discharged into the chamber 35 from which the fuel elements may be removed through a gate valve 89. The reactor is surrounded by a concrete shield 96, and the space between the reactor and the shield is filled with water. Figs. 10 and 11 show a cross-section and plan of fuel elements in a fuel channel in the moderator bricks 41. The uranium plates 49 are spaced apart by lugs 50 and rest on a ledge 48 in a cylindrical graphite cartridge 40. The cartridge is provided with a throat 46 to restrict the flow of coolant gas, and the areas of these constrictions are varied at different parts of the lattice to secure the most efficient heat removal from the system. The thickness of the uranium plates 49 is also varied; those which are used in the centre of the lattice are thinner, to provide a greater cooling surface, than those near the outside. The reactor includes five safety rods and four control rods, of which one is shown in Fig. 23 ; this comprises two concentric tubes arranged so that cooling water can circulate through them. The positions of the control rods may be controlled automatically to maintain a constant neutron flux. The helium leaving the reactor may pass through a heat exchanger to a filter which removes any solid fission products entrained by the helium, and thence through a compressor back to the reactor. Specifications 817,751 and 817,752 are referred to.
GB5513/46A 1945-02-16 1946-02-21 Nuclear reactor Expired GB817754A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US817754XA 1945-02-16 1945-02-16

Publications (1)

Publication Number Publication Date
GB817754A true GB817754A (en) 1959-08-06

Family

ID=22166315

Family Applications (1)

Application Number Title Priority Date Filing Date
GB5513/46A Expired GB817754A (en) 1945-02-16 1946-02-21 Nuclear reactor

Country Status (1)

Country Link
GB (1) GB817754A (en)

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110097979A (en) * 2018-01-31 2019-08-06 中国辐射防护研究院 A kind of graphite dust capturing device for pebble bed high temperature reactor
CN110097989A (en) * 2018-01-31 2019-08-06 中国辐射防护研究院 It is a kind of to remove graphite dust pollution method for pebble bed high temperature reactor
CN111561576A (en) * 2020-05-14 2020-08-21 北京利方达真空技术有限责任公司 Vacuum gate valve with neutron shielding function
US11450443B1 (en) 2021-03-16 2022-09-20 Austin Lo Structured plasma cell energy converter for a nuclear reactor
US11574745B2 (en) 2020-09-21 2023-02-07 Austin Lo System and method for energy conversion using an aneutronic nuclear fuel
US11798698B2 (en) 2020-12-04 2023-10-24 Austin Lo Heavy ion plasma energy reactor

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110097979A (en) * 2018-01-31 2019-08-06 中国辐射防护研究院 A kind of graphite dust capturing device for pebble bed high temperature reactor
CN110097989A (en) * 2018-01-31 2019-08-06 中国辐射防护研究院 It is a kind of to remove graphite dust pollution method for pebble bed high temperature reactor
CN110097979B (en) * 2018-01-31 2022-11-18 中国辐射防护研究院 Graphite dust collecting device for ball bed high-temperature gas cooled reactor
CN110097989B (en) * 2018-01-31 2022-11-18 中国辐射防护研究院 Graphite dust pollution removing method for pebble-bed high-temperature gas cooled reactor
CN111561576A (en) * 2020-05-14 2020-08-21 北京利方达真空技术有限责任公司 Vacuum gate valve with neutron shielding function
US11574745B2 (en) 2020-09-21 2023-02-07 Austin Lo System and method for energy conversion using an aneutronic nuclear fuel
US11798698B2 (en) 2020-12-04 2023-10-24 Austin Lo Heavy ion plasma energy reactor
US11450443B1 (en) 2021-03-16 2022-09-20 Austin Lo Structured plasma cell energy converter for a nuclear reactor
US11842820B2 (en) 2021-03-16 2023-12-12 Austin Lo Structured plasma cell energy converter for a nuclear reactor

Similar Documents

Publication Publication Date Title
US2857324A (en) Engineering test reactor
US3235463A (en) Nuclear reactor
US3725199A (en) Nuclear reactor organization and fuel assembly arrangement
US3275521A (en) Fast breeder reactor arrangement
GB883678A (en) Nuclear reactor fuel element
NL282482A (en)
GB847902A (en) Means and method of changing the neutron density curve across a nuclear reactor
US3228852A (en) Nuclear reactor
US3809610A (en) Nuclear fuel assembly with bypass coolant control
GB1034997A (en) Nuclear reactor
US3437558A (en) Nuclear reactor and refueling cell arrangement
US3085966A (en) Liquid homogeneous fuel element and reactor therefor
GB817754A (en) Nuclear reactor
US2921007A (en) Thermal neutronic reactor
US3149043A (en) Nuclear reactor
GB951658A (en) Improvements in or relating to swimming-pool nuclear reactors
US3271262A (en) Nuclear reactor with improved fuel handling facility
GB1092107A (en) Nuclear reactor
GB979937A (en) Nuclear reactor
US3271260A (en) Liquid metal fast breeder reactor
US3341420A (en) Modular flux trap reactor
US2954335A (en) Neutronic reactor
Kim et al. Design characteristics and startup tests of HANARO: The newly in-service Korean research reactor
GB913653A (en) Improvements in or relating to nuclear reactors
GB1135396A (en) Improvements in or relating to fluid cooled nuclear reactors