G21D   1/00  \	0	0	2G077	G21D   1/00	99	ϥץȤκ¤ǣģ	Details of nuclear power plant (control G21D 3/00)
G21D   1/00  A	0	0	2G077	G21D   1/00	99	ѷϵ	Cooling system equipment
G21D   1/00  P	0	1	2G077	G21D   1/00	145	䵡ѷ	Cooling system auxiliary equipment
G21D   1/00  Q	0	1	2G077	G21D   1/00	369	Ǯ򴹴	heat exchangers
G21D   1/00  R	0	1	2G077	G21D   1/00	206	ϡ̼塤ӿ	for sea water (such as water-intake and drain)
G21D   1/00  S	0	1	2G077	G21D   1/00	643	ȯ	steam generators
G21D   1/00  B	0	0	2G077	G21D   1/00	496	۴	Piping
G21D   1/00  H	0	1	2G077	G21D   1/00	336	ٻޤɻ	support or splash prevention
G21D   1/00  J	0	1	2G077	G21D   1/00	141	ǮݲޤǮ	heat insulation, hot insulation, or thermal transfer
G21D   1/00  C	0	0	2G077	G21D   1/00	108	۴ɴ	Pipe through sections
G21D   1/00  L	0	1	2G077	G21D   1/00	323	ή۴ɴ	fluid pipe through sections
G21D   1/00  M	0	1	2G077	G21D   1/00	251	ɴ	conduit through sections
G21D   1/00  E	0	0	2G077	G21D   1/00	229	ɥ˴ؤ	Related to drain
G21D   1/00  F	0	0	2G077	G21D   1/00	110	ðޤƬ	Pressure devices or peak pressure reduction devices
G21D   1/00  G	0	0	2G077	G21D   1/00	81	̶ϡǷ	Compressed air system; nitrogen system
G21D   1/00  T	0	0	2G077	G21D   1/00	227	󥯡¢ӥԥå	Tanks, storage, and pits
G21D   1/00  U	0	0	2G077	G21D   1/00	88	˴ؤ	Related to seals
G21D   1/00  V	0	0	2G077	G21D   1/00	208	ۤ˴ؤ	Related to valves
G21D   1/00  K	0	1	2G077	G21D   1/00	101	Υۤ˴ؤ	Related to main valves for separating steams
G21D   1/00  N	0	1	2G077	G21D   1/00	161	ƨۤޤϰۤ˴ؤ	Related to escape or safety valves
G21D   1/00  W	0	0	2G077	G21D   1/00	482	忩ɻߤ˴ؤ	Related to prevention of erosion
G21D   1/00  X	0	0	2G077	G21D   1/00	527	ӣк˴ؤ	Related to SC countermeasures
G21D   1/00  Y	0	0	2G077	G21D   1/00	430	㸺˴ؤ	Related to exposure
G21D   1/00  Z	0	0	2G077	G21D   1/00	183	¾Τ	Others
G21D   1/02  \	1	1	2G077	G21D   1/02	12	°	Arrangements of auxiliary equipment
G21D   1/02  A	1	0	2G077	G21D   1/02	49	ζ°ϧ˴ؤ	Related to liquid-metal cooled reactors
G21D   1/02  B	1	1	2G077	G21D   1/02	54	Сե	over-flow systems
G21D   1/02  C	1	1	2G077	G21D   1/02	85	ǮͽǮ֡棳	heating and preheating devices (control
G21D   1/02  D	1	1	2G077	G21D   1/02	13	굤ִ	air bleed and replacement of gases
G21D   1/02  E	1	1	2G077	G21D   1/02	31	°㸺	metal steam reduction devices
G21D   1/02  F	1	1	2G077	G21D   1/02	30	Խʪ̣ǣͥ	removing impurities
G21D   1/02  G	1	1	2G077	G21D   1/02	12	Ÿǥʥȥꥦν̣ǣͥ	removing and processing solidified sodium
G21D   1/02  H	1	1	2G077	G21D   1/02	85	ʥȥꥦǼ谷ι¤	construction of storage and handling room of sodium
G21D   1/02  J	1	1	2G077	G21D   1/02	11	ʥȥꥦνŶ	filling and supplying of sodium
G21D   1/02  K	1	1	2G077	G21D   1/02	33	ʥȥꥦβ	collection of sodium
G21D   1/02  L	1	1	2G077	G21D   1/02	18	ʥȥꥦή̷	circulation system of sodium
G21D   1/02  M	1	1	2G077	G21D   1/02	30	ʥȥꥦ谷	sodium handling devices
G21D   1/02  N	1	1	2G077	G21D   1/02	46	С	cover gas system
G21D   1/02  S	1	0	2G077	G21D   1/02	15	ȥͥ	Main steam tunnel
G21D   1/02  T	1	0	2G077	G21D   1/02	539	ӥϡ̼ʬʬΥæ	Turbine condensate system (moisture content separators, desalters)
G21D   1/02  U	1	0	2G077	G21D   1/02	65	æޤ϶д	Deairing or air ejectors
G21D   1/02  Z	1	0	2G077	G21D   1/02	42	¾Τ	Others
G21D   1/04  \	1	1	2G077	G21D   1/04	327	ݥ׷ϤιʸϧƴμʤˤΣǣã	Pumping arrangements (by means within the reactor pressure vessel G21C 15/24)
G21D   3/00  \	0	0	2G077	G21D   3/00	55	ϥץȤʸҳȿǣã	Control of nuclear power plant (control of nuclear reaction&nbsp;G21C 7/00)
G21D   3/00  B	0	0	2G077	G21D   3/00	252	žޤϱžٱ̰۾ˤΣǣģɽžˤΣǣģ	Administration or assistance of operation (at failure G21D3/04; at failure G21D3/04, at load follow operation G21D3/12)
G21D   3/00  E	0	0	2G077	G21D   3/00	158	ϥץȤεư	Activation of nuclear power plant
G21D   3/00  G	0	0	2G077	G21D   3/00	34	ϥץȤ	Termination of  nuclear power plant
G21D   3/00  H	0	0	2G077	G21D   3/00	60	ϥץȤαž	Operation and control of nuclear power plant
G21D   3/00  A	0	1	2G077	G21D   3/00	137	Ϥ	control of output
G21D   3/00  D	0	1	2G077	G21D   3/00	72	ӥϤټǡϷ۾ˤΣǣģɽžˤΣǣģ	control of turbine systems (at load shutdown and at failure of electric systems G21D3/04; at load follow operation G21D3/12)
G21D   3/00  J	0	2	2G077	G21D   3/00	21	ǮʬʬΥ˴ؤ	related to reheaters and moisture separators
G21D   3/00  C	0	0	2G077	G21D   3/00	64	̾ȯ֤οΤΤΣǣģ	Control of water supply (for controlling water level for steam generators G21D3/08)
G21D   3/00  K	0	1	2G077	G21D   3/00	26	°αž̶۵ޡΥ߻θϧѷϤǣã	operation control of a set of attachments and equipment (control of the reactor cooling system during emergency, separation, or shutdown)
G21D   3/00  L	0	2	2G077	G21D   3/00	22	ˤ	in condensers
G21D   3/00  M	0	2	2G077	G21D   3/00	37	Ǯˤ	in feed water heaters
G21D   3/00  N	0	2	2G077	G21D   3/00	57	ϤˤΡΤΤ	in purification systems; for cleaning
G21D   3/00  P	0	2	2G077	G21D   3/00	22	եϤˤ	in offgas systems
G21D   3/00  Q	0	2	2G077	G21D   3/00	15	ðˤ	in pressurisers
G21D   3/00  R	0	1	2G077	G21D   3/00	20	ƱεǽͭϤ˴Ϣ	Related to systems having the same function
G21D   3/00  S	0	0	2G077	G21D   3/00	22	ʣθϥץȤ˴Ϣ뱿ž	Operation and control related to a plurality of nuclear power plants
G21D   3/00  Z	0	0	2G077	G21D   3/00	30	¾Τ	Others
G21D   3/02  \	1	1	2G077	G21D   3/02	17	ư	Manual control
G21D   3/04  \	1	1	2G077	G21D   3/04	38	ʸϧζ۵ɸǣã	Safety arrangements (emergency protection of reactor G21C 9/00)
G21D   3/04  B	1	0	2G077	G21D   3/04	193	۾֡Τн褹뤿αžٱ	Operation support devices to deal with emergencies and accidents
G21D   3/04  A	1	0	2G077	G21D   3/04	132	ݸϡɻߡϤ¿Ųʤħͭ	Characterized by multiplexing means for safety protect systems, prevention of wrong scrams, and control systems
G21D   3/04  C	1	0	2G077	G21D   3/04	27	ңӣӡʱ֡	RSS (remote stop device)
G21D   3/04  D	1	0	2G077	G21D   3/04	65	Ϥεưءߤħͭ	Characterized by safety arrangements, and activation, switching, and termination of control systems
G21D   3/04  E	1	0	2G077	G21D   3/04	38	ݥפݸ	Protecting pumps
G21D   3/04  F	1	0	2G077	G21D   3/04	15	ӥݸ	Protecting turbines
G21D   3/04  G	1	0	2G077	G21D   3/04	45	ۡΥۤϳɻߡ˴ؤ	Related to prevention and control of safety and separation valves
G21D   3/04  H	1	0	2G077	G21D   3/04	67	۾֡Τн褹뤿αž	Operation and control to deal with faulty conditions and accidents
G21D   3/04  J	1	1	2G077	G21D   3/04	40	ԣףӡʥ༺Ԥβϸݡˤн褹	dealing with ATWS (temporary event when scram fails)
G21D   3/04  K	1	1	2G077	G21D   3/04	34	Ϥ㲼뤳Ȥˤꥹ򤹤	avoiding scram by reducing output
G21D   3/04  L	1	1	2G077	G21D   3/04	47	Ϥΰ۾н褹	dealing with the failures of water supply systems
G21D   3/04  M	1	2	2G077	G21D   3/04	12	Ǯΰ۾н褹	dealing with failures in feed water heaters
G21D   3/04  N	1	1	2G077	G21D   3/04	78	ݥפΰ۾н褹	dealing with failures in pumps
G21D   3/04  P	1	1	2G077	G21D   3/04	81	Ѻࡢʪϳ̤н褹ΡѺήɻ߼ʤƴħΤΣǣãϧ۵ѷϣǣãǣã	Characterized by dealing with the leakage of coolants and radioactive materials (vessels that are means to prevent coolants from leaking)
G21D   3/04  Q	1	1	2G077	G21D   3/04	196	ޤϳŸӼн褹ΡŸ	dealing with power lost inside or outside of sites; power facilities
G21D   3/04  R	1	1	2G077	G21D   3/04	86	ټǡϷΰ۾н褹	dealing with load shutdown and failures in power systems
G21D   3/04  S	1	2	2G077	G21D   3/04	28	ħͭ	Characterized by output control
G21D   3/04  T	1	2	2G077	G21D   3/04	58	ӥϤħͭ	Characterized by the control of turbine systems
G21D   3/04  U	1	1	2G077	G21D   3/04	96	Ͽ̤н褹	dealing with earthquakes
G21D   3/04  V	1	1	2G077	G21D   3/04	35	кҤн褹ΡϧƴǼƴʳƴ۵Ѥ	dealing with fires; cooling down vessels, equipment and the like other than reactor and containment vessels
G21D   3/04  Z	1	0	2G077	G21D   3/04	18	¾Τ	Others
G21D   3/06  \	2	2	2G077	G21D   3/06	32	ץλΤ˴ΡʸϧλΤ˴Σǣã	responsive to faults within the plant (in the reactor G21C 9/02)
G21D   3/08  \	1	1	2G077	G21D   3/08	30	ץȤγƥѥ᡼	Regulation of any parameters in the plant
G21D   3/08  A	1	0	2G077	G21D   3/08	86	̵岹١ϧ١	Temperature control (supply water temperature, temperature around the access to a reactor)
G21D   3/08  H	1	1	2G077	G21D   3/08	38	ϧƴ⡢ˤΡʥɥꥢ󥯤ޤࡣʲƱ͡	within reactor vessels and around the access (including calandria tanks; the same shall apply hereinafter)
G21D   3/08  J	1	1	2G077	G21D   3/08	42	ƴ۴ɡβǮͽǮ˴ؤ	Related to heating and preheating vessels, pipes, and devices
G21D   3/08  B	1	0	2G077	G21D   3/08	63	ήϧή̡ή̡	Discharge control (discharge of a core and of water supply)
G21D   3/08  K	1	1	2G077	G21D   3/08	55	ϧήʺƽ۴ήϣǣãͥ	discharge control of a core (control of recirculating discharge
G21D   3/08  D	1	0	2G077	G21D   3/08	94	ϧ	Pressure control (core pressure; main steam pressure)
G21D   3/08  L	1	1	2G077	G21D   3/08	103	ȯ֡ʸϧƴȯɥˤˤ	at steam generating equipment  (such as reactor vessels, steam generators, and steam drums)
G21D   3/08  E	1	0	2G077	G21D   3/08	75	٥	Level control
G21D   3/08  M	1	1	2G077	G21D   3/08	25	ϧƴˤΡưѾȯΤϽ	at reactor vessels (excluding what generates steam for power)
G21D   3/08  N	1	1	2G077	G21D   3/08	20	ȯ֡ʸϧƴȯɥˤˤ	at steam generating equipment  (such as reactor vessels, steam generators, and steam drums)
G21D   3/08  P	1	2	2G077	G21D   3/08	33	ˤ	by water supply control
G21D   3/08  Q	1	3	2G077	G21D   3/08	53	ħͭ	Characterized by control methods
G21D   3/08  R	1	4	2G077	G21D   3/08	81	ǡʿ̡̡ή̡桢ñǡʿ̡ˤ	by three elements (water level, steam quantity, water supply discharge) control and single element (water level) control
G21D   3/08  S	1	4	2G077	G21D   3/08	32	ƽ۴ķϤαžθ	considering operation and control of recirculating systems
G21D   3/08  T	1	4	2G077	G21D   3/08	88	ݥסۤεưءߤθ	considering activation, switching, and termination of pumps and valves
G21D   3/08  U	1	4	2G077	G21D   3/08	16	Ϥΰ۾н褹	dealing with failures in instrumentation and control systems
G21D   3/08  V	1	3	2G077	G21D   3/08	29	ߥ˥ޥեžץȤεư߻ˤ	during minimal flow operation, and start and shutdown of plants
G21D   3/08  W	1	3	2G077	G21D   3/08	49	ݥסۤεưءߤħͭ	Characterized by start, switching, and stop of pumps and valves
G21D   3/08  F	1	0	2G077	G21D   3/08	243	ǳǻ	Control of burnable gas concentration
G21D   3/08  G	1	0	2G077	G21D   3/08	435	Ѻʬǻ٤̻ǻ١ǻ١	Control of the concentration of each component in a coolant (oxygen concentration; hydrogen concentration)
G21D   3/08  X	1	1	2G077	G21D   3/08	244	ǡǡǿ뤳Ȥˤǡǻ٤椹	controlling the concentration of hydrogen and oxygen by injecting or removing hydrogen, oxygen, or hydrogen peroxide
G21D   3/08  Z	1	0	2G077	G21D   3/08	9	¾Τ	Others
G21D   3/10  \	2	2	2G077	G21D   3/10	7	«Ƴ줿ѿ¾ѿ㡥١ѺήϤƳ줿ѿȤ礵뤳Ȥˤ	by a combination of a variable derived from neutron flux with other controlling variables, e.g. derived from temperature, cooling flow, pressure
G21D   3/12  \	2	2	2G077	G21D   3/12	29	ưϵؤ٤ˤΤ߱ƸϧԤʤ	by adjustment of the reactor in response only to changes in engine demand
G21D   3/12  B	2	0	2G077	G21D   3/12	66	٥ѥײ衢ɽžٱ	Load pattern planning; load follow operation support equipment
G21D   3/12  A	2	0	2G077	G21D   3/12	21	ϧȯǮľѤץȤɽž	Load follow operation of a plant directly using heat generated in reactors
G21D   3/12  C	2	1	2G077	G21D   3/12	106	ƽ۴ήؼʤȤѤΤޤˡӥˤ	recirculating discharge control (including control using control rods as alternative means); by turbine control
G21D   3/12  D	2	1	2G077	G21D   3/12	19	ˤ	by control rods
G21D   3/12  E	2	2	2G077	G21D   3/12	48	Ӻƽ۴ήϢѤ	using recirculating discharge control  in conjunction with control rods
G21D   3/12  F	2	0	2G077	G21D   3/12	67	ϧȯǮȯǮ򴹴𤷤ƴŪѤץȤɽž	load follow operation of a plant indirectly using heat generated in reactors through heat generators, heat exchangers, and the like
G21D   3/12  Z	2	0	2G077	G21D   3/12	3	¾Τ	Others
G21D   3/14  \	3	3	2G077	G21D   3/14	8	ѺήѲ	Varying flow of coolant
G21D   3/16  \	3	3	2G077	G21D   3/16	4	ȿ٤Ѳ	Varying reactivity
G21D   3/18  \	2	2	2G077	G21D   3/18	1	ȿ٤ѲΤߤ˱ƸϧγΥץȤ椹뤳Ȥˤ	by adjustment of plant external to the reactor only in response to change in reactivity
G21D   5/00  \	0	0	2G077	G21D   5/00	34	ϧȯǮ򵡳Ūͥ륮Ѵ븶ϧưϵؤι	Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
G21D   5/02  \	1	1	2G077	G21D   5/02	23	ϧưϵؤι¤ȹ礻㡥·	Reactor and engine structurally combined, e.g. portable
G21D   5/04  \	1	1	2G077	G21D   5/04	16	¤礷Ƥʤϧưϵ	Reactor and engine not structurally combined
G21D   5/06  \	2	2	2G077	G21D   5/06	346	غưΤϧ۴Ĥ	with engine working medium circulating through reactor core
G21D   5/08  \	2	2	2G077	G21D   5/08	252	غưΤǮ򴹴ǸϧѺˤǮ	with engine working medium heated in a heat exchanger by the reactor coolant
G21D   5/10  \	3	3	2G077	G21D   5/10	15	ξưΤϧǰǮ졤ϧγǮ㡥Ǯˤ	Liquid working medium partially heated by reactor and vaporised by heat source external to the core, e.g. with oil heating
G21D   5/12  \	3	3	2G077	G21D   5/12	58	ξưΤϧѺˤ	Liquid working medium vaporised by reactor coolant
G21D   5/14  \	4	4	2G077	G21D   5/14	61	ˡϧѺˤäƲǮ	and also superheated by reactor coolant
G21D   5/16  \	4	4	2G077	G21D   5/16	16	̤ߤ줿ǮˤǮ	superheated by separate heat source
G21D   7/00  \	0	0	2G077	G21D   7/00	23	ͻޤϳʬȿľȯŤԤʤιŵͥ륮Σǣȣ	Arrangements for direct production of electric energy from fusion or fission reactions (obtaining electric energy from radioactive sources G21H 1/00)
G21D   7/02  \	1	1	2G077	G21D   7/02	10	ͣȣȯ֤Ѥ	using magneto-hydrodynamic generators
G21D   7/04  \	1	1	2G077	G21D   7/04	52	ǮǻҤѤΡǳǮǻҤȤι¤ȹ礻ǣã	using thermoelectric elements (structural combination of fuel element with thermoelectric element G21C 3/40)
G21D   9/00  \	0	0	2G077	G21D   9/00	208	ưϤؤθ򴹰ʳŪ㡥ʪ˼ΤǮ򶡵뤹빽	Arrangements to provide heat for purposes other than conversion into power, e.g. for heating buildings
