(0)G21C:0/3:
IPC6
SECTION G - PHYSICS
NUCLEAR REACTORS
G21C
1/4
<<   >>   G21C001/00 - G21C003/64  

G 21 C

NUCLEAR REACTORS (analogue computers therefor G 06 G 7/54; fusion reactors G 21 B; nuclear explosives G 21 J)

 

 

 

 

1
/ 00 Reactors

1
/ 01 General details not provided for in groups G 21 C 3/00 to G 21 C 19/00 [3]  

1
/ 02 Fast fission reactors, i.e. reactors not using a moderator  

1
/ 03 cooled by a coolant not essentially pressurised, e.g. pool-type reactors [5]  

1
/ 04 Thermal reactors  

1
/ 06 Heterogeneous reactors, i.e. in which fuel and moderator are separated  

1
/ 07 Pebble-bed reactors; Reactors with granular fuel [5]  

1
/ 08 moderator being highly pressurised, e.g. boiling-water reactor, integral-superheat reactor, pressurised-water reactor (G 21 C 1/22 takes precedence)  

1
/ 09 Pressure regulating arrangements, i.e. pressurisers [5]  

1
/ 10 moderator and coolant being different or separated  

1
/ 12 moderator being solid, e.g. Magnox reactor  

1
/ 14 moderator being substantially not pressurised, e.g. swimming-pool reactor (G 21 C 1/22 takes precedence)  

1
/ 16 moderator and coolant being different or separated, e.g. sodium-graphite reactor  

1
/ 18 coolant being pressurised  

1
/ 20 moderator being liquid, e.g. pressure-tube reactor  

1
/ 22 using liquid or gaseous fuel  

1
/ 24 Homogeneous reactors, i.e. in which fuel and moderator present an effectively homogeneous medium to the neutrons  

1
/ 26 Single-region reactors  

1
/ 28 Two-region reactors  

1
/ 30 Subcritical reactors  

1
/ 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 (G 21 C 1/02 to G 21 C 1/30 take precedence) [3]  
 

3
/ 00 Reactor fuel elements or their assemblies; Selection of substances for use as reactor fuel elements

3
/ 02 Fuel elements  

3
/ 04 Constructional details  

3
/ 06 Casings; Jackets  

3
/ 07 characterised by their material, e.g. alloys [5]  

3
/ 08 provided with external means to promote heat-transfer, e.g. fins, baffles, corrugations  

3
/ 10 End closures  

3
/ 12 Means forming part of the element for locating it within the reactor core; External spacers for this purpose  

3
/ 14 Means forming part of the element for inserting it into, or removing it from, the core; Means for coupling adjacent elements  

3
/ 16 Details of the construction within the casing  

3
/ 17 Means for storage or immobilisation of gases in fuel elements [5]  

3
/ 18 Internal spacers or other non-active material within the casing, e.g. compensating for expansion of fuel rods or for compensating excess reactivity (interlayers G 21 C 3/20)  

3
/ 20 with coating on fuel or on inside of casing; with non-active interlayer between casing and active material  

3
/ 22 with fissile or breeder material in contact with coolant  

3
/ 24 with fissile or breeder material in fluid form within a non-active casing  

3
/ 26 with fissile or breeder material in powder form within a non-active casing  

3
/ 28 with fissile or breeder material in solid form within a non-active casing  

3
/ 30 Assemblies of a number of fuel elements in the form of a rigid unit  

3
/ 32 Bundles of parallel pin-, rod-, or tube-shaped fuel elements  

3
/ 322 Means to influence the coolant flow through or around the bundles [5]  

3
/ 324 Coats or envelopes for the bundles [5]  

3
/ 326 comprising fuel elements of different composition; Comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods [5]  

3
/ 328 Relative disposition of the elements in the bundle lattice [5]  

3
/ 33 Supporting or hanging of elements in the bundle (spacer grids G 21 C 3/34); Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles [5]  

3
/ 332 Supports for spacer grids [5]  

3
/ 334 Assembling the bundles [5]  

3
/ 335 Exchanging elements in irradiated bundles [5]  

3
/ 336 Spacer elements for fuel rods in the bundle (spacer grids G 21 C 3/34) [5]  

3
/ 338 Helicoidal spacer elements [5]  

3
/ 34 Spacer grids  

3
/ 344 formed of assembled tubular elements [5]  

3
/ 348 formed of assembled non-intersecting strips [5]  

3
/ 352 formed of assembled intersecting strips [5]  

3
/ 356 being provided with fuel element supporting members [5]  

3
/ 36 Assemblies of plate-shaped fuel elements or coaxial tubes  

3
/ 38 Fuel units consisting of a single fuel element in a supporting sleeve  

3
/ 40 Structural combination of fuel element with thermoelectric element for direct production of electric energy from fission heat (for temperature measurement G 21 C 17/10)  

3
/ 42 Selection of substances for use as reactor fuel  

3
/ 44 Fluid or fluent reactor fuel  

3
/ 46 Aqueous compositions  

3
/ 48 True or colloidal solutions of the active constituent  

3
/ 50 Suspensions of the active constituent; Slurries  

3
/ 52 Liquid metal compositions  

3
/ 54 Fused salt, oxide, or hydroxide compositions  

3
/ 56 Gaseous compositions; Suspensions in a gaseous carrier  

3
/ 58 Solid reactor fuel  

3
/ 60 Metallic fuel; Intermetallic dispersions  

3
/ 62 Ceramic fuel  

3
/ 64 Ceramic dispersion fuel, e.g. cermet  

<< >>
1 1 4