GB817754A - Nuclear reactor - Google Patents
Nuclear reactorInfo
- 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
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous 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
- G21C1/10—Heterogeneous 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
- G21C1/12—Heterogeneous 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
-
- 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
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.
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)
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 |
-
1946
- 1946-02-21 GB GB5513/46A patent/GB817754A/en not_active Expired
Cited By (9)
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 |