摘要:
A high temperature gas cooled reactor steam generation system (1) includes a nuclear reactor (2) that has helium gas as a primary coolant and heats the primary coolant by heat generated by a nuclear reaction that decelerates neutrons by a graphite block, a steam generator (3) that has water as a secondary coolant and heats the secondary coolant by the primary coolant via the nuclear reactor (2) to generate steam, a steam turbine (4) that is operated by the steam from the steam generator (3), and a generator (5) that generates electricity according to an operation of the steam turbine (4). Moreover, the system (1) includes pressure adjustment means for setting a pressure of the secondary coolant in the steam generator (3) to be lower than a pressure of the primary coolant in the nuclear reactor (2).
摘要:
In a nuclear power plant making use of a high temperature gas cooled reactor, it is necessary, prior to commencing power generation and connection of a generator to an electrical distribution grid, to condition the power generation circuit of the plant. This involves creating stable conditions within the power generation circuit. To this end, the plant includes a start-up blower system for circulating working fluid, typically helium, around the power generation circuit until the desired conditions are satisfied. The start-up blower system typically includes a normally open in-line valve, at least one blower connected in parallel with the in-line valve and a normally closed isolation valve connected in series with the blower. Conditioning the power generation circuit will typically include stabilizing the pressure in the circuit at between 10 bar and 50 bar.
摘要:
An improved gas circulatorfor a gas-cooled nuclear reactor system is disclosed which includes a stator, a rotor having a rotor shaft, and an impeller attached to one end thereof. A radial active magnetic bearing and a radial backup bearing are positioned proximate each end of the rotor shaft. An axial active magnetic bearing is also located between the ends of the rotor shaft, as is an axial backup bearing, with two of the backup bearings enclosed within a sealed chamber that may contain a lubricant, for example, a solid lubricant or a liquid lubricant. Preferably, the gas circulator is installed in a nuclear reactor system with the rotor shaft in a substantially vertical orientation and the sealed chamber near the bottom of the rotor shaft. The lower radial backup bearing and the axial backup bearing are advantageously located within the sealed chamber. The lower radial backup bearing and the axial backup bearing may be spaced apart sufficiently to permit the lower radial backup bearing to provide substantially all radial support for the rotor when the radial active magnetic bearings are deenergized.
摘要:
The present invention relates to nuclear technology and is intended for use in power-generating systems with a fast reactor cooled by a liquid-metal coolant which is primarily in the form of molten lead or an alloy thereof. The problem addressed by the invention consists in reducing the specific volume of lead coolant per unit of power of the reactor and in increasing the safety of the reactor. The system comprises a reactor cavity (1) with an upper cover (2), an arranged within the cavity (1) reactor having an active zone (4), steam generators (5), circulation pumps (7), circulation conduits (8) and (9), actuating mechanism systems and devices for starting up, operating and shutting down the reactor system, wherein the steam generators (5) are in the form of tubular heat exchangers in which the lead coolant (10) flows within the pipes, while the water-steam flows in a space between the pipes, the steam generators (5) are arranged in separate boxes (6) and communicate with the reactor cavity (1) by means of circulation conduits for raising (8) and discharging (9) the lead coolant (10), the steam generators (5) and most of the circulation conduits (8) and (9) are arranged higher than the level of the lead coolant (10) within the reactor cavity (1), and the circulation pumps (7) are arranged within the reactor cavity (1) on the circulation conduits (8) and (9) for raising the "hot" lead coolant, and a technical means (13) is provided for ensuring intrinsic circulation of the lead coolant (10) through the active zone (4) when the circulation pumps (7) are switched off.
摘要:
An improved gas circulatorfor a gas-cooled nuclear reactor system is disclosed which includes a stator, a rotor having a rotor shaft, and an impeller attached to one end thereof. A radial active magnetic bearing and a radial backup bearing are positioned proximate each end of the rotor shaft. An axial active magnetic bearing is also located between the ends of the rotor shaft, as is an axial backup bearing, with two of the backup bearings enclosed within a sealed chamber that may contain a lubricant, for example, a solid lubricant or a liquid lubricant. Preferably, the gas circulator is installed in a nuclear reactor system with the rotor shaft in a substantially vertical orientation and the sealed chamber near the bottom of the rotor shaft. The lower radial backup bearing and the axial backup bearing are advantageously located within the sealed chamber. The lower radial backup bearing and the axial backup bearing may be spaced apart sufficiently to permit the lower radial backup bearing to provide substantially all radial support for the rotor when the radial active magnetic bearings are deenergized.
摘要:
The present invention relates to nuclear technology and is intended for use in power-generating systems with a fast reactor cooled by a liquid-metal coolant which is primarily in the form of molten lead or an alloy thereof. The problem addressed by the invention consists in reducing the specific volume of lead coolant per unit of power of the reactor and in increasing the safety of the reactor. The system comprises a reactor cavity (1) with an upper cover (2), an arranged within the cavity (1) reactor having an active zone (4), steam generators (5), circulation pumps (7), circulation conduits (8) and (9), actuating mechanism systems and devices for starting up, operating and shutting down the reactor system, wherein the steam generators (5) are in the form of tubular heat exchangers in which the lead coolant (10) flows within the pipes, while the water-steam flows in a space between the pipes, the steam generators (5) are arranged in separate boxes (6) and communicate with the reactor cavity (1) by means of circulation conduits for raising (8) and discharging (9) the lead coolant (10), the steam generators (5) and most of the circulation conduits (8) and (9) are arranged higher than the level of the lead coolant (10) within the reactor cavity (1), and the circulation pumps (7) are arranged within the reactor cavity (1) on the circulation conduits (8) and (9) for raising the "hot" lead coolant, and a technical means (13) is provided for ensuring intrinsic circulation of the lead coolant (10) through the active zone (4) when the circulation pumps (7) are switched off.
摘要:
A high temperature gas cooled reactor steam generation system (1) includes a nuclear reactor (2) that has helium gas as a primary coolant and heats the primary coolant by heat generated by a nuclear reaction that decelerates neutrons by a graphite block, a steam generator (3) that has water as a secondary coolant and heats the secondary coolant by the primary coolant via the nuclear reactor (2) to generate steam, a steam turbine (4) that is operated by the steam from the steam generator (3), and a generator (5) that generates electricity according to an operation of the steam turbine (4). Moreover, the system (1) includes pressure adjustment means for setting a pressure of the secondary coolant in the steam generator (3) to be lower than a pressure of the primary coolant in the nuclear reactor (2).
摘要:
In a nuclear power plant making use of a high temperature gas cooled reactor, it is necessary, prior to commencing power generation and connection of a generator to an electrical distribution grid, to condition the power generation circuit of the plant. This involves creating stable conditions within the power generation circuit. To this end, the plant includes a start-up blower system for circulating working fluid, typically helium, around the power generation circuit until the desired conditions are satisfied. The start-up blower system typically includes a normally open in-line valve, at least one blower connected in parallel with the in-line valve and a normally closed isolation valve connected in series with the blower. Conditioning the power generation circuit will typically include stabilizing the pressure in the circuit at between 10 bar and 50 bar.
摘要:
A reactor core cooling structure of the present invention comprises cooling gas flow-in slits (9a) for making a cooling gas flow in a circular reactor core, which slits are provided at an outer graphite cylinder (2a) for covering an outside of the circular reactor core; cooling gas flow-out slits (10a) for making the cooling gas flow in a circular reactor core, which slits are provided at an inner graphite cylinder (3a) for covering an inside of the circular reactor core; a circular cooling gas flow path (5a) that is provided at an outside of the outer graphite cylinder, and is connected to an inlet piping (7a) of the cooling gas at a foot of the outer graphite cylinder; and an inner cooling gas flow path (6a) that is provided at an inside of the inner graphite cylinder, and is connected to an outlet piping (8a) of the cooling gas at a foot of the inner graphite cylinder.