Method for controlling secondary side pressure relief accidents of all vapor generators
A technology of steam generator and control method, which is applied in the field of reactor control, and can solve the problems of containment temperature and pressure rise, heat transfer tube thermal shock, nuclear power rise, etc.
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Embodiment 1
[0063] Such as figure 1 As shown, the existing nuclear power plant system includes: reactor, steam generator (can be more than one), and steam turbine. The device is equipped with auxiliary water supply and exhaust steam bypass. The secondary circuit is equipped with an isolation valve that can be activated for isolation when the circuit breaks. The primary circuit is equipped with a safety injection system and a normal waste heat discharge system.
[0064] Such as figure 2 As shown, the general route of the present invention is: first use the measurable data of the system to make a judgment, obtain the cause of the secondary side pressure relief accident, perform the corresponding troubleshooting operation according to the cause, and then determine the execution according to the success of the troubleshooting operation. Differently, the steam generator is used to lower the temperature and pressure of the primary circuit system. In order to quickly and accurately realize th...
Embodiment 2
[0079] Further examples are:
[0080] The feedwater control operation includes: starting the auxiliary feedwater of the steam generator, closing the auxiliary feedwater of the steam generator, and adjusting the flow rate of the auxiliary feedwater of the steam generator;
[0081] The exhaust steam control operation includes: starting the exhaust steam bypass of the steam generator, closing the exhaust steam bypass of the steam generator, and adjusting the steam discharge flow of the steam generator.
[0082] Further examples are:
[0083] S31 is specifically:
[0084] Carry out feed water control operation on the intact steam generator until the water loading is restored;
[0085] When the state parameter of the primary circuit reaches the safety injection termination condition, turn to the safety injection system corresponding to the reactor coolant system to terminate the operation;
[0086] After the safety injection system is terminated, turn to the intact steam generat...
Embodiment 3
[0107] to attach figure 1 And attached figure 2 For example:
[0108] When an uncontrolled pressure drop accident occurs on the secondary side of all steam generators in a nuclear power plant, before the operator does not intervene, the emergency shutdown signal that occurs during the accident triggers the emergency shutdown and the ad hoc safety device activation signal that appears Trigger safety systems including safety injection system and auxiliary water supply system into operation.
[0109] After the operator intervenes, the operation is carried out according to the specific content of the present invention, the detailed content is as follows:
[0110] (1) Determine the cause of the accident based on the important status parameters and equipment status of the nuclear power plant. The specific method is to combine the changes in the pressure and water content of the steam generator, the changes in the internal environment of the containment, the valves and Identify t...
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