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.
摘要:
A post-accident fission product removal system (100) may include an air mover (104), a filter assembly (106), and/or an ionization chamber (116). The air mover (104) may be configured to move contaminated air (102) through the filter assembly (106) to produce filtered air (115). The ionization chamber (116) may be connected to the filter assembly (106). The ionization chamber (116) may include an anode (118) and a cathode (120). The ionization chamber (116) may be configured to receive the filtered air (115) from the filter assembly (106) and to ionize and capture radioisotopes from the filtered air (115) to produce clean air (124).
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 pump leakage mitigation device includes one or more clamp arms (120) on an outer surface of a pump (10) that can be driven by a biasing element (110) to seat against a shaft (11) of the pump (10) to seal or reduce fluid flow through a breakdown of the pump (10). The biasing element (110) engages only at threshold temperatures, such as those associated with breakdown orifice failure (12) when additional sealing may be necessary. Clamp arms (120) of any number and shape can be used to achieve the desired seal and based on the pump geometry. A sealant surface (125) and/or keeping mechanism are useable with the leakage mitigation device to enhance fluid flow blockage throughout a pump failure transient scenario. Pump leakage mitigation devices are installed on an outside of a variety of different pump types and can thus be installed, actuated, manipulated, disengaged, and/or removed without having to destroy or disassemble the pump (10).
摘要:
A post-accident fission product removal system (100) may include an air mover (104), a filter assembly (106), and/or an ionization chamber (116). The air mover (104) may be configured to move contaminated air (102) through the filter assembly (106) to produce filtered air (115). The ionization chamber (116) may be connected to the filter assembly (106). The ionization chamber (116) may include an anode (118) and a cathode (120). The ionization chamber (116) may be configured to receive the filtered air (115) from the filter assembly (106) and to ionize and capture radioisotopes from the filtered air (115) to produce clean air (124).
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.