摘要:
A heat transfer system (400) for a nuclear plant may include a piping system (418) that includes first and second connectors (414, 416), heat exchanger (406), pump (402), and power source (420). The heat transfer system (400) may not be connected to the plant during normal power operations. The power source (420) may be independent of a normal electrical power distribution system for the plant and may be configured to power the pump (402). The piping system (418) may be configured to connect the heat exchanger (406) and pump (402). The connectors (414, 416) may be configured to connect the heat transfer system (400) to a fluid system (500, 600) of the plant. When the connectors connect the heat transfer system (400) to the fluid system, the heat transfer system (400) may be configured to receive fluid from the fluid system (500, 600) of the plant via the first connector (414), to pump the fluid through the heat exchanger (406), and to return the fluid to the fluid system (500, 600) via the second connector (416).
摘要:
A method and apparatus for providing an alternative remote spent fuel pool cooling system for the spent fuel pool (10). The cooling system (20) is operated to cool the spent fuel pool (10) in the event of a plant accident when normal plant electricity is not available for the conventional fuel pool cooling and cleanup system, or when the integrity of the spent fuel (12) has been jeopardized. The cooling system (20) is operated and controlled from a remote location, which is ideal during a plant emergency.
摘要:
A method and apparatus 20 for providing an alternative cooling system for the suppression pool 2 of a Boiling Water Reactor (BWR) nuclear reactor 1. The cooling system 20 is operated to cool the suppression pool 2 in the event of a plant accident when normal plant electricity is not available for the conventional residual heat removal system and pumps. The cooling system 20 may also be used to supplement the cooling of the suppression pool 2 via the residual heat removal system. The cooling system 20 is operated and controlled from a remote location, which is ideal during a plant emergency.
摘要:
A method and system for external alternate suppression pool cooling for a Boiling Water Nuclear Reactor (BWR) that does not breach the Mark I primary containment. The external cooling system may include a heat sink (20) fluidly coupled to cooling coils (26) surrounding the suppression pool (2). Cool water may be pumped through the cooling coils (26) without the need for normal plant electrical power, which is ideal during a plant emergency. The cooling system (30) may also be operated and controlled from a remote location to protect the safety of plant personnel.
摘要:
A method and apparatus for measuring a liquid level (10c) of a Spent Fuel Pool (10) of a Light Water Reactor without using electrical power. The method and apparatus may use a pressurized gas source (14) connected to tubing (12) or piping that may discharge near the bottom of the Spent Fuel Pool (10). The system may include a flow meter (16) and throttle valve (18) that may be used to determine a required gas pressure to provide a specified flow rate of gas for known Spent Fuel Pool water levels. By obtaining calibration data points of pressure and flow for multiple Spent Fuel Pool water levels, a calibration curve may be obtained that allows for the measurement of Spent Fuel Pool liquid level using the system, without the need for electrical power.
摘要:
A method and apparatus for measuring a liquid level (10c) of a Spent Fuel Pool (10) of a Light Water Reactor without using electrical power. The method and apparatus may use a pressurized gas source (14) connected to tubing (12) or piping that may discharge near the bottom of the Spent Fuel Pool (10). The system may include a flow meter (16) and throttle valve (18) that may be used to determine a required gas pressure to provide a specified flow rate of gas for known Spent Fuel Pool water levels. By obtaining calibration data points of pressure and flow for multiple Spent Fuel Pool water levels, a calibration curve may be obtained that allows for the measurement of Spent Fuel Pool liquid level using the system, without the need for electrical power.
摘要:
A method and system for external alternate suppression pool cooling for a Boiling Water Nuclear Reactor (BWR) that does not breach the Mark I primary containment. The external cooling system may include a heat sink (20) fluidly coupled to cooling coils (26) surrounding the suppression pool (2). Cool water may be pumped through the cooling coils (26) without the need for normal plant electrical power, which is ideal during a plant emergency. The cooling system (30) may also be operated and controlled from a remote location to protect the safety of plant personnel.
摘要:
A heat transfer system (400) for a nuclear plant may include a piping system (418) that includes first and second connectors (414, 416), heat exchanger (406), pump (402), and power source (420). The heat transfer system (400) may not be connected to the plant during normal power operations. The power source (420) may be independent of a normal electrical power distribution system for the plant and may be configured to power the pump (402). The piping system (418) may be configured to connect the heat exchanger (406) and pump (402). The connectors (414, 416) may be configured to connect the heat transfer system (400) to a fluid system (500, 600) of the plant. When the connectors connect the heat transfer system (400) to the fluid system, the heat transfer system (400) may be configured to receive fluid from the fluid system (500, 600) of the plant via the first connector (414), to pump the fluid through the heat exchanger (406), and to return the fluid to the fluid system (500, 600) via the second connector (416).
摘要:
A method and system (40) for an alternate energy removal path for a reactor pressure vessel (RPV) of a light water reactor. A pair of manually operated containment isolation valves (36), one located inside and one located outside of primary containment (7), are used to open and close a steam extraction line (30) that is fluidly coupled between the RPV and a heat sink (32). The heat sink is located outside of primary containment. A source of external electrical power is not required to operate the system or perform the method.