GB1097745A - Improvements in or relating to nuclear reactors - Google Patents
Improvements in or relating to nuclear reactorsInfo
- Publication number
- GB1097745A GB1097745A GB23491/65A GB2349165A GB1097745A GB 1097745 A GB1097745 A GB 1097745A GB 23491/65 A GB23491/65 A GB 23491/65A GB 2349165 A GB2349165 A GB 2349165A GB 1097745 A GB1097745 A GB 1097745A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- core
- gas
- coolant
- pressure vessel
- 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
- G21C1/32—Integral 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
- G21C1/322—Integral 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 above the core
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
- G21C1/022—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
- G21C1/028—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a pressurised coolant
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/02—Biological shielding ; Neutron or gamma shielding
- G21C11/022—Biological shielding ; Neutron or gamma shielding inside the reactor vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
-
- 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)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Life Sciences & Earth Sciences (AREA)
- Health & Medical Sciences (AREA)
- Biomedical Technology (AREA)
- General Health & Medical Sciences (AREA)
- Molecular Biology (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
1,097,745. Reactors. GENERAL DYNAMICS CORPORATION. June 2, 1965 [June 15, 1964], No. 23491/65. Heading G6C. A fast fission reactor is gas cooled and has housed within its prestressed concrete pressure vessel coolant circulators, steam generators, and conduits for passing gas from the core to the steam generators. The pressure vessel is cylindrical, and the circumferential and axial prestressing bands are connected to jacks which continuously measure and adjust the strain in each band; thus, should an explosion occur in the vessel, the concrete will crack and open to vent the pressure, after which the band strains will be automatically adjusted to close the cracks before radioactive material escapes to a dangerous extent. General construction (Fig. 1)-The pressure vessel comprises an inner part containing axial prestressing members 42, and an outer part containing the radial prestressing members 40. The inner part contains cooling tubes 66 adjacent to a steel lining 62 covered by thermal insulation 64. A concrete shield 46 with access plug 74 divides the vessel interior into two compartments. The lower compartment contains the core 50 and associated all-surrounding breeder blanket, and fuel handling machinery 127, 128. The upper compartment contains blowers 56, driven by steam from their associated boilers, steam generating heat exchangers 106, 108, 110, control rod drives 82, and an emergency water coolant tank 121, this tank is connected to the gas coolant conduits leading to the core by conduits 125 containing diaphragms 126 which are ruptured when a predetermined pressure different arises between gas conduits 58 and space 37 through which the gas passes from the heat exchangers to the circulators (tank 121 is vented at 124). To ensure that a reduction in reactivity takes place when the core is flooded with water, the core includes a small amount of a resonance neutron absorber such as gadolinium, indium, samarium, gold, or mixtures of these materials. Wherever possible, e.g. thermal shielding 86, porous concrete is utilized within the pressure vessel, in order to assist in explosion and pressure surge damping; expansion tanks can also be associated with the pressure vessel interior. The boron control rods incorporate iron or stainless steel follow-up sections. The coolant is preferably helium, but could alternatively be carbon dioxide or nitrogen. The Fuel handling system comprises a machine 127, a catch pot 128, a fuel supply tube 129 leading to a top face gas lock 130, spent fuel shoot and storage corral 131, 134, and fuel handling machine room 138 in which the machine is normally stored. The catch pot includes a mechanism for lowered used fuel assemblies into itself from the core, and is also able to receive new fuel assemblies from the tube 129. Refuelling can be conducted either with reactor top dome 145 removed and main sealing plug 44 in position with air being circulated instead of the normal coolant, or with the core water flooded and plugs 44 and 74 removed. The fuel comprises Pu 230 and Pu 240 and the fertile material U.238, the fuel being present as an oxide; alternatively, thorium can be used as the fertile material. The fuel can alterntively be used in carbide, phosphide or silicide form. The fuel elements, which are made up into fuel assemblies, comprise elongate cylindrical cans with central fuel portions and end blanket portions. The fuel is in the form of cylindrical pellets which are axially based to facilitate the migration of fission product gases to gas reservoirs in the tops of the fuel elements. Fine texture roughing is carried out on the can exteriors to improve heat transfer. Fuel assemblies and support.-Referring also to Fig. 7 (Figs. 4 to 6, not shown, are relevent), the fuel elements are assembled by being supported on a grid structure 190 at their lower ends and located at their upper ends by a similar grid 176. Intermediate straps (200) are also used. The grids are attached to a square section tube (26) in the upper end of which is mounted a plate 172 and a clamping unit 162, 164, 166. The core top from which the fuel assemblies are hung comprises a plurality of deep webs 94 forming a number of square section pockets into each of which a substantial portion of the length of fuel assembly is pulled. Diagonal webs 152 carry bosses into which the fuel assembly clamping units are drawn.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US37490864A | 1964-06-15 | 1964-06-15 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1097745A true GB1097745A (en) | 1968-01-03 |
Family
ID=23478691
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB23491/65A Expired GB1097745A (en) | 1964-06-15 | 1965-06-02 | Improvements in or relating to nuclear reactors |
Country Status (8)
Country | Link |
---|---|
AT (1) | AT284979B (en) |
BE (1) | BE665449A (en) |
CH (1) | CH447401A (en) |
DE (1) | DE1489920B1 (en) |
FR (1) | FR1448885A (en) |
GB (1) | GB1097745A (en) |
NL (1) | NL6507640A (en) |
SE (1) | SE346650B (en) |
Family Cites Families (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2864754A (en) * | 1954-05-03 | 1958-12-16 | Callery Chemical Co | Preparation of tetraborane |
DE1852483U (en) * | 1957-04-06 | 1962-05-30 | Bbc Brown Boveri & Cie | GAS-COOLED REACTOR. |
FR1273532A (en) * | 1959-11-24 | 1961-10-13 | Licentia Gmbh | Device placed in the pressure-resistant casing of a nuclear reactor to reduce the pressure of the vapor which develops during the bursting of part of the primary circuit |
NL265705A (en) * | 1960-06-08 |
-
1965
- 1965-06-02 GB GB23491/65A patent/GB1097745A/en not_active Expired
- 1965-06-11 AT AT530065A patent/AT284979B/en active
- 1965-06-14 FR FR20610A patent/FR1448885A/en not_active Expired
- 1965-06-14 SE SE07802/65A patent/SE346650B/xx unknown
- 1965-06-15 CH CH828565A patent/CH447401A/en unknown
- 1965-06-15 BE BE665449A patent/BE665449A/xx unknown
- 1965-06-15 DE DE1965G0043878 patent/DE1489920B1/en active Pending
- 1965-06-15 NL NL6507640A patent/NL6507640A/xx unknown
Also Published As
Publication number | Publication date |
---|---|
NL6507640A (en) | 1965-12-16 |
CH447401A (en) | 1967-11-30 |
BE665449A (en) | 1965-10-01 |
AT284979B (en) | 1970-10-12 |
DE1489920B1 (en) | 1969-12-18 |
FR1448885A (en) | 1966-08-12 |
SE346650B (en) | 1972-07-10 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US3151034A (en) | Consolidated nuclear steam generator arrangement | |
US3235463A (en) | Nuclear reactor | |
GB883678A (en) | Nuclear reactor fuel element | |
GB857959A (en) | Power breeder reactor | |
US3211621A (en) | Heterogeneous breeder or converter type neutronic reactor | |
US3438857A (en) | Containment vessel construction for nuclear power reactors | |
US3296085A (en) | Calandria core for sodium graphite reactor | |
GB913658A (en) | Improvements in or relating to fuel element assembly for nuclear reactors | |
US3128234A (en) | Modular core units for a neutronic reactor | |
US3212986A (en) | Three tank separate superheat reactor | |
US3186913A (en) | Graphite moderated nuclear reactor | |
US3079321A (en) | Sodium deuterium reactor | |
GB1018541A (en) | Nuclear reactor | |
US3357892A (en) | Gas cooled nuclear reactor | |
JPH032276B2 (en) | ||
US3475272A (en) | Gas-cooled fast reactor | |
GB1169714A (en) | Nuclear Reactor Fuel Elements | |
US3461034A (en) | Gas-cooled nuclear reactor | |
US3271260A (en) | Liquid metal fast breeder reactor | |
US3211623A (en) | Neutronic reactor and fuel element therefor | |
GB962625A (en) | Nuclear reactor | |
GB1088787A (en) | Heat extraction device for a reactor | |
GB867454A (en) | Gas-cooled neutronic reactor | |
GB1097745A (en) | Improvements in or relating to nuclear reactors | |
US3342689A (en) | Liquid-moderated, gas-cooled nuclear reactor and pressure equalization system |