Control system for plant

• US 9,558,856 B2
• Filed: 08/02/2011
• Issued: 01/31/2017
• Est. Priority Date: 08/12/2010
• Status: Active Grant

• Current Assignee: Mitsubishi Heavy Industries, Ltd.
• Original Assignee: Mitsubishi Heavy Industries, Ltd.
• Inventors: Nagai, Tetsuro, Satake, Hidekazu
• Primary Examiner(s): Keith, Jack W
• Assistant Examiner(s): Davis, Sharon M
• Application Number:
  US13/816,172
• Publication Number:
  US 20130136222A1
• Time in Patent Office: 2,009 Days
• Field of Search: 376/215, 376/216, 376/217, 376/219
• US Class Current: 1/1
• CPC Class Codes: G21C 7/00 Control of nuclear reaction
• CPC Class Codes: G21D 3/00 Control of nuclear power plant control of nuclear reaction in general G21C7/00
• CPC Class Codes: G21D 3/001 Computer implemented control
• CPC Class Codes: G21D 3/007 Expert systems
• CPC Class Codes: G21D 3/04 Safety arrangements emergency protection of reactor G21C9/00
• CPC Class Codes: Y02E 30/00 Energy generation of nuclear origin
• CPC Class Codes: Y02E 30/30 Nuclear fission reactors

Abstract

In a control system for a plant controlling a plant such as a nuclear power plant 1 with use of a plurality of digital control devices 41, the plurality of digital control devices 41 include a plurality of control functions 46 to 56, and the plurality of control functions 46 to 56 are provided in the plurality of digital control devices 41 in a distributed manner so that the digital control devices 41 may not fall below safety standards preset by safety analyses. This provides a control system for a plant using the plurality of digital control devices 41 and configured to control a plant safely even when a digital control device is failed.

Claims

1. A control system for a nuclear power plant, the nuclear power plant including a nuclear reactor cooling system including a nuclear reactor and a turbine system performing heat exchange with the nuclear reactor cooling system, comprising:

a first digital control device including a first programmable processor configured to perform a first feed water control function, a first main steam relief valve control function, a pressurizer interlock function, a main feed water pump speed control function, and a second main steam relief valve interlock function;

a second digital control device including a second programmable processor configured to perform a second feed water control function, a second main steam relief valve control function, a pressurizer pressure control function, and a third main steam relief valve interlock function;

a third digital control device including a third programmable processor configured to perform a third feed water control function, a third main steam relief valve control function, a pressurizer water level control function, and a fourth main steam relief valve interlock function;

a fourth digital control device including a fourth programmable processor configured to perform a fourth feed water control function, a fourth main steam relief valve control function, a control rod shutdown margin monitor function, and a first main steam relief valve interlock function;

a fifth digital control device including a fifth programmable processor configured to perform a turbine bypass control function, a control rod interlock function and a boron concentration control function; and

a sixth digital control device including a sixth programmable processor configured to perform a control rod driving control function and a turbine bypass interlock function,

wherein the control rod driving control function, the control rod interlock function, the boron concentration control function, and the control rod shutdown margin monitor function are control functions related to the output of the nuclear reactor,

wherein the first through fourth feed water control functions, the first through fourth main steam relief valve control functions, the first through fourth main steam relief valve interlock functions, the turbine bypass control function, and the main feed water pump speed control function are control functions related to heat removal of the turbine system, and

wherein the pressurizer pressure control function and the pressurizer interlock function are control functions related to the pressure of the nuclear reactor cooling system,

wherein the first through fourth programmable processors are configured to perform the first through fourth feed water control functions, respectively, to avoid simultaneous occurrence of abnormalities in any two of the first through fourth feed water control functions,

wherein the first through fourth programmable processors are configured to perform the first through fourth main steam relief valve control functions, respectively, to avoid simultaneous occurrence of abnormalities in any two of the first through fourth main steam relief valve control functions,

wherein the fourth, first, second and third programmable processors are configured to perform the first, second, third and fourth main steam relief valve interlock functions, respectively, to avoid simultaneous occurrence of abnormalities in any two of the first through fourth main steam relief valve interlock functions,

wherein the first through fourth programmable processors are configured to perform the first through fourth main steam relief valve control functions, respectively, and the fourth, first, second and third programmable processors are configured to perform the first through fourth main steam relief valve interlock functions, respectively, to avoid simultaneous occurrence of abnormalities in any one of the first through fourth main steam relief valve control functions and any one of the first through fourth main steam relief valve interlock functions, respectively,

wherein the fifth programmable processor and the sixth programmable processor are configured to perform the turbine bypass control function and the turbine bypass interlock function, respectively, to avoid simultaneous occurrence of abnormalities in the turbine bypass control function and the turbine bypass interlock function,

wherein the second programmable processor and the first programmable processor are configured to perform the pressurizer pressure control function and the pressurizer interlock function, respectively, to avoid simultaneous occurrence of abnormalities in the pressurizer pressure control function and the pressurizer interlock function,

wherein the sixth programmable processor and the fifth programmable processor are configured to perform the control rod driving control function and the control rod interlock function, respectively, to avoid simultaneous occurrence of abnormalities in the control rod driving control function and the control rod interlock function, and

wherein the sixth programmable processor is configured to perform the control rod driving control function to avoid simultaneous occurrence of abnormalities in the control rod driving control function and the first through fourth feed water control functions performed by the first through fourth programmable processors, respectively; and

wherein the fifth programmable processor and the fourth programmable processor are configured to perform the boron concentration control function and the control rod shutdown margin monitor function, respectively, to avoid simultaneous occurrence of abnormalities in the boron concentration control function and the control rod shutdown margin monitor function.

2. The control system for a nuclear power plant according to claim 1, wherein the first through fourth programmable processors are configured such that when one of the first through fourth programmable processors fails to disable one of the first through fourth feed water control functions, respectively, the other programmable processors can control the other feed water control functions.

3. The control system for a nuclear power plant according to claim 1, wherein the first through fourth programmable processors are configured such that when one of the first through fourth programmable processors fails to cause one of the first through fourth main steam relief valve control functions to be actuated properly, the main steam relief valve interlock control function of the others of the first through fourth programmable processors lock control of the main steam relief valve control functions.

4. The control system for a nuclear power plant according to claim 1, wherein the first through fourth programmable processors are configured such that when one of the first through fourth programmable processors fails to disable its main steam relief valve interlock control function, the main steam relief valve control function of the others of the first through fourth programmable processors controls the main steam relief valve interlock control function.

5. The control system for a nuclear power plant according to claim 1, wherein the fifth and sixth programmable processors are configured such that when the fifth programmable processor fails to cause the turbine bypass control function to be actuated properly, the turbine bypass interlock function of the sixth programmable processor locks control of the turbine bypass control function.

6. The control system for a nuclear power plant according to claim 1, wherein the fifth and sixth programmable processors are configured such that when the sixth programmable processor fails to disable the turbine bypass interlock function, the turbine bypass control function of the fifth programmable processor performs suitable control.

7. The control system for a nuclear power plant according to claim 1, wherein the second and first programmable processors are configured such that when the second programmable processor fails to cause the pressurizer pressure control function to be actuated properly, the pressurizer interlock function of the first programmable processor locks control of the pressurizer pressure control function.

8. The control system for a nuclear power plant according to claim 1, wherein the second and first programmable processors are configured such that when the first programmable processor fails to disable the pressure interlock function, the pressurizer pressure control function of the second programmable processor performs suitable control.

9. The control system for a nuclear power plant according to claim 1, wherein the sixth and fifth programmable processors are configured such that when the sixth programmable processor fails to cause the control rod driving control function to be actuated properly, the control rod interlock function of the fifth programmable processor locks control of the control rod driving control function.

10. The control system for a nuclear power plant according to claim 1, wherein the sixth and fifth programmable processors are configured such that when the fifth programmable processor fails to disable the control rod interlock function, the control rod driving control function of the sixth programmable processor performs suitable control.

11. The control system for a nuclear power plant according to claim 1, wherein the sixth programmable processor is configured to perform the control rod driving control function and the first though fourth programmable processors are configured to perform first through fourth feed water control functions, respectively, such that when the sixth programmable processor fails to cause the control rod driving function to be actuated properly, the first through fourth feed water control functions of the first through fourth programmable processors, respectively, control a main feed water system to control pressure of the nuclear reactor cooling system.

12. The control system for a nuclear power plant according to claim 1, wherein the sixth programmable processor is configured to perform the control rod driving control function and the first though fourth programmable processors are configured to perform first through fourth feed water control functions, respectively, such that when one of the first through fourth digital control devices fails to disable the feed water control function, the sixth programmable processor controls the control rod driving function to control pressure of the nuclear reactor cooling system.

13. The control system for a nuclear power plant according to claim 1, wherein the fourth and fifth programmable processors are configured such that when the fourth programmable processor fails to disable the control rod margin monitor function, the boron concentration control function of the fifth programmable processor controls boron concentration to control nuclear reactions.

14. The control system for a nuclear power plant according to claim 1, wherein the fourth and fifth programmable processors are configured such that when the fifth programmable processor fails to disable the boron concentration control function, the fourth programmable processor controls the control rod margin monitor function to monitor a shutdown margin of the nuclear reactor by the control rods.

15. The control system for a nuclear power plant as a plant according to claim 1, wherein

the nuclear power plant includes a plurality of steam generators connected to the nuclear reactor, and a plurality of main feed water systems configured to supply a coolant to the respective steam generators, and

the first through fourth feed water control functions control the respective main feed water systems.

16. The control system for a nuclear power plant as a plant according to claim 1, wherein

the first main steam relief valve control function, the second main steam relief valve control function, the third main steam relief valve control function, the fourth main steam relief valve control function, the pressurizer pressure control function, the turbine bypass control function and the control rod driving control function are actuation control functions that control actuation of respective units provided in the nuclear power plant, and

the first main steam relief valve interlock function, the second main steam relief valve interlock function, the third main steam relief valve interlock function, the fourth main steam relief valve interlock function, the pressurizer interlock function, the turbine bypass interlock function and the control rod interlock function are functions that lock actuation control by the actuation control functions.

17. The control system for a nuclear power plant as a plant according to claim 1, wherein

the nuclear reactor houses therein a fuel assembly, a control rod driving unit configured to drive a control rod to be inserted in the fuel assembly, a steam generator connected to the nuclear reactor, and a main feed water system configured to supply a coolant to the steam generator, and

the control rod driving control function controls the control rod driving unit and the first through fourth feed water control functions respectively control the main feed water system.

18. The control system for a nuclear power plant as a plant according to claim 1, wherein

the nuclear reactor houses therein a fuel assembly and a control rod to be inserted in the fuel assembly and a boron concentration control unit configured to control boron concentration in a coolant circulating in the nuclear reactor, and

the control rod shutdown margin monitor function monitors a shutdown margin of the nuclear reactor by the control rod and the boron concentration control function controls the boron concentration control unit.

19. The control system for a nuclear power plant as a plant according to claim 1, wherein each of the plurality of digital control devices includes a plurality of the programmable processors.