摘要:
A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an integral pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the integral pressurizer. The drive shaft passes through a vessel penetration of the pressure vessel that is at least large enough for the impeller to pass through.
摘要:
A pressurizer spray apparatus with half-circle type nozzles, which is provided in a pressurizer of a pressurized light-water reactor type nuclear power plant, includes a spray inlet pipe penetrating the pressurizer from outside to inside and having a hollow tube shape, a spray ring arranged inside the pressurizer and having a ring shape and a hollow tube shape, a connecting pipe connecting the spray ring and the spray inlet pipe and having a hollow tube shape, and a spray nozzle provided on an outer circumferential surface of the spray ring and capable of discharging a low-temperature coolant into the pressurizer.
摘要:
An integral pressurized light water reactor having most of the components of a primary side of a pressurized water reactor nuclear steam supply system housed in a single pressure vessel with a pressurizer separated from the remaining reactor system by a surge separator having multiple layers of separated steel plates with a number of concentric baffles extending therebetween. A circuitous flow path is provided through and between the plates and concentric baffles and a relatively stagnant pool of coolant is maintained within an innermost zone between the plates to provide thermal isolation.
摘要:
This invention relates to a system for regulating a liquid in a circuit, with the system comprising: a plug valve comprising at least one inlet and one outlet, the plug comprising an internal passage through which is intended to pass the liquid flowing from the inlet to the outlet of the valve when the valve is open at least partially, an expansion reservoir in communication with the liquid flowing in the circuit and intended to contain liquid and a compensating gas, characterised in that the plug comprises at least partially an expansion channel which has at least one lateral opening located on a lateral face of the plug and which is conformed to provide a permanent communication between said lateral opening and the expansion reservoir, the valve being conformed in such a way that: at least when the valve is closed: the lateral opening is in direct communication with the liquid coming from the inlet or from the outlet of the valve, when the valve is open at least partially, the lateral opening cooperates with an inner wall integral with a body of the valve in such a way as to form a conduit in communication on the one hand with the expansion reservoir and on the other hand with the internal passage. The invention also relates to a circuit integrating this system as well as a use of this system.
摘要:
A treatment of a heater tube intended to be used in a pressurizer of the primary cooling system of a nuclear reactor. In particular, the heater tube comprises a heater housed in a substantially cylindrical sheath. The material of which this sheath is made is a work-hardened austenitic stainless steel. In particular, the external surface of the sheath is liable to undergo a stress corrosion during use of the heatertube. The method includes a heat treatment step, preferably using induction heating, in which the external surface of the sheath is heat-treated so as to recrystallize the material of the sheath at least on the surface thereof.
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:
A method for working on a defective heating element of a pressuriser comprising a tank lying flat along a longitudinal axis and elongate heating elements extending within the tank, and at least one spacer plate through which the heating elements pass and which is capable of maintaining a transverse spacing between the heating elements is provided. The method includes cutting at least one spacer plate around the heating element so as to detach said heating element from said spacer plate, and then extracting the heating element from the tank in one single piece.
摘要:
An integral pressurized light water reactor having most of the components of a primary side of a pressurized water reactor nuclear steam supply system housed in a single pressure vessel with a pressurizer separated from the remaining reactor system by a surge separator having multiple layers of separated steel plates with a number of concentric baffles extending therebetween. A circuitous flow path is provided through and between the plates and concentric baffles and a relatively stagnant pool of coolant is maintained within an innermost zone between the plates to provide thermal isolation.
摘要:
In the present invention, a reactor power control apparatus of a natural circulation reactor comprises a power control apparatus for controlling reactor power and a pressure control apparatus for controlling reactor pressure. A power adjustment demand signal S4 is input from the power control apparatus into the pressure control apparatus. The pressure control apparatus controls degree of opening of a inlet port steam control valve provided in a moisture separation heater that is connected to a low-pressure turbine, based on the power adjustment demand signal S4.A reactor power control apparatus of the natural circulation reactor can suppress reactor power variation and obtain stable power.
摘要:
The method for filling water into and changing the air of a main circuit of a water-cooled nuclear reactor includes a step of placing a connection and fluid isolation device which is connected to a hot leg of each cooling loop of the main circuit so as to substantially insulate, from inside the vessel, the assembly of hot legs. The method also includes a step of injecting water through an injection circuit on at least one hot leg until each cooling loop is filled with water having changed the air from a steam generator and until the water level in the vessel reaches above the side openings of the vessel that correspond to the loops, after which the connecting device is taken out of the vessel. The connecting device is capable of using telescopic connection elements.