ISLAND MODE FOR NUCLEAR POWER PLANT
First Claim
1. A nuclear power plant comprising:
- a nuclear reactor comprising a pressurized water reactor (PWR) and a steam generator configured to transfer heat from primary coolant water heated by the PWR to secondary coolant water in order to convert the secondary coolant water to steam;
a turbine connected with the steam generator to be driven by steam output by the steam generator;
an electric generator connected with the turbine to be driven by the turbine to generate electricity;
an electrical switchyard receiving electrical power from the electrical power generator during normal operation of the nuclear power plant;
a condenser connected with the turbine to condense steam exiting the turbine; and
a turbine bypass system configured to transfer a quantity of steam output by the steam generator to the condenser without passing through the turbine responsive to loss of offsite electrical power to the nuclear power plant wherein the quantity of steam transferred to the condenser without passing through the turbine is effective to (1) allow the nuclear reactor to power down without triggering steam generator or nuclear reactor pressurizer safety valve setpoints and (2) continue powering house electrical loads of the nuclear power plant using the turbine.
6 Assignments
0 Petitions
Accused Products
Abstract
A nuclear power plant comprises a pressurized water reactor (PWR) and a steam generator driving a turbine driving an electric generator. A condenser condenses steam after flowing through the turbine. Responsive to a station blackout, the nuclear power plant is electrically isolated and a bypass valve is opened to convey bypass steam flow from the steam generator to the condenser without flowing through the turbine. The thermal power output of the PWR is gradually reduced over the transition time interval. After opening, the bypass valve is gradually closed over the transition time interval. A supplemental bypass valve may also be opened responsive to the station blackout to convey supplemental bypass steam flow from the steam generator to a feedwater system supplying secondary coolant feedwater to the steam generator. The supplemental bypass steam flow does not flow through the turbine and does not flow through the condenser.
13 Citations
24 Claims
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1. A nuclear power plant comprising:
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a nuclear reactor comprising a pressurized water reactor (PWR) and a steam generator configured to transfer heat from primary coolant water heated by the PWR to secondary coolant water in order to convert the secondary coolant water to steam; a turbine connected with the steam generator to be driven by steam output by the steam generator; an electric generator connected with the turbine to be driven by the turbine to generate electricity; an electrical switchyard receiving electrical power from the electrical power generator during normal operation of the nuclear power plant; a condenser connected with the turbine to condense steam exiting the turbine; and a turbine bypass system configured to transfer a quantity of steam output by the steam generator to the condenser without passing through the turbine responsive to loss of offsite electrical power to the nuclear power plant wherein the quantity of steam transferred to the condenser without passing through the turbine is effective to (1) allow the nuclear reactor to power down without triggering steam generator or nuclear reactor pressurizer safety valve setpoints and (2) continue powering house electrical loads of the nuclear power plant using the turbine. - View Dependent Claims (2, 3, 4, 5, 6, 7, 8, 9)
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10. A method of operating a nuclear power plant that includes a pressurized water reactor (PWR), a steam generator, a turbine, an electric generator, and a condenser, the method comprising:
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operating the PWR to heat primary coolant flowing through a nuclear reactor core comprising fissile material immersed in the primary coolant water; operating the steam generator to convert secondary coolant feedwater to steam using primary coolant water heated by the operating PWR; operating the turbine by flowing steam from the steam generator through the turbine and then through the condenser; driving the electric generator using the turbine to generate electricity; conveying the generated electricity to an electrical switchyard; and responsive to a station blackout, transitioning the nuclear power plant to an island mode over a transition time interval by transition operations including; at the beginning of the transition time interval, disconnecting the electric generator from the electrical switchyard and opening a bypass valve to convey bypass steam flow from the steam generator to the condenser wherein the bypass steam flow does not flow through the turbine; after opening the bypass valve, gradually closing the bypass valve over the transition time interval; and gradually reducing the thermal power output of the PWR over the transition time interval. - View Dependent Claims (11, 12, 13, 14, 15, 16, 17, 18)
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19. A method operating in conjunction with a nuclear power plant comprising a pressurized water reactor (PWR) operating to heat primary coolant water, a steam generator using the heated primary coolant water to convert secondary coolant feedwater to steam, a turbine driven by steam from the steam generator and operatively connected with an electric generator, and a condenser connected with the turbine to condense steam after flowing through the turbine, the method comprising:
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transitioning the nuclear power plant to an island mode over a transition time interval by transition operations including; responsive to detecting a station blackout, electrically isolating the nuclear power plant and opening a bypass valve to convey bypass steam flow from the steam generator to the condenser without flowing through the turbine; and gradually reducing the thermal power output of the PWR over the transition time interval. - View Dependent Claims (20, 21, 22, 23, 24)
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Specification