A multi-loop natural circulation experimental device under six-degree-of-freedom motion conditions and a method therefor are provided. The device includes: a six-degree-of-freedom motion simulation platform; a multi-loop main circulation loop including a serpentine pre-heater, an experimental section, two sleeve-type condensers, and a pressurized circulating pump, a voltage stabilizer and related equipment; and a cooling water system including a sleeve condenser, a plate heat exchanger, a cooling tower, a cooling fan, a cooling water tank and related equipment; and an electric heating system including a DC power supply, a low voltage power controller and a transformer. The present invention also provides an experimental method of the device.

A multi-loop natural circulation experimental device under six-degree-of-freedom motion conditions and a method therefor are provided. The device includes: a six-degree-of-freedom motion simulation platform; a multi-loop main circulation loop including a serpentine pre-heater, an experimental section, two sleeve-type condensers, and a pressurized circulating pump, a voltage stabilizer and related equipment; and a cooling water system including a sleeve condenser, a plate heat exchanger, a cooling tower, a cooling fan, a cooling water tank and related equipment; and an electric heating system including a DC power supply, a low voltage power controller and a transformer. The present invention also provides an experimental method of the device.

The present invention relates to a method for identifying the unit causing a raw water leak in a condenser of a thermal power plant consisting of n units.

The invention relates to safe operation support systems of nuclear power plants (NPPs) at severe accidents, including methods and systems for cooling and cooling control of the reactors molten core. The invention increases safety of NPP and cooling efficiency of the molten core of a reactor. The invention increases the efficiency of cooling the molten core of a reactor by safely removing the heat load from the molten metal mirror, ensuring the elimination of vapor explosions. The invention changes the principle of cooling the reactor molten core, in that after the molten core destroys the reactor vessel, the conditions for subsequent cooling of the molten metal are determined by the characteristics of the trap casing, but not of the reactor.

A method for replacing a cesium trap includes freezing the cesium trap which partially contains cesium and is located within a shielded cell and. The cesium trap is then decoupled and removed from the shielded cell. A second cesium trap is inserted into the shielded cell and attached to the shielded cell.

A method for replacing a cesium trap includes freezing the cesium trap which partially contains cesium and is located within a shielded cell and. The cesium trap is then decoupled and removed from the shielded cell. A second cesium trap is inserted into the shielded cell and attached to the shielded cell.

A nuclear power plant comprising a primary coolant circuit, a steam-water circuit separated from the primary coolant circuit and a steam generator connected to the primary coolant circuit and the steam-water circuit to transfer heat from the primary coolant circuit into the steam-water circuit has at least one dosing point in the steam-water circuit to inject a reducing agent into the steam-water circuit, wherein the reducing agent is an organic compound consisting of carbon, hydrogen and oxygen. Furthermore, a method for operating said nuclear power plant and the use of the method for downtime preservation of the secondary side of a steam generator of a nuclear power plant are provided.

An acousto-optic leakage monitoring system for main steam pipeline in nuclear power plant. The system includes an acoustic emission leakage monitoring loop and a spectrum leakage monitoring loop, wherein the signal input ends of the acoustic emission leakage monitoring loop and the signal input ends of the spectrum leakage monitoring loop are respectively arranged at detection points of the main steam pipeline. The signal output ends of the acoustic emission leakage monitoring loop and the signal output ends of the spectrum leakage monitoring loop are communicatively connected to each other through a network switch, and the network switch is sequentially connected with a control unit and a display unit. Compared with the prior art, the acousto-optic leakage monitoring system for the main steam pipeline in nuclear power plant according to the present invention provides early warning before the main steam pipeline leaks and realizes the diversity and redundancy of the main steam pipeline leakage monitoring methods by combining acoustic emission and spectroscopy, so that the detection results are more credible, and the maintenance cost after installation is extremely low. The detection sensitivity is higher and the response time is shortened, which significantly improves the response speed after leakage is found and provides a larger safety margin.

A device for measuring a total gas content of a primary circuit of a PWR nuclear power plant includes a shielding protective cover, and a sampling assembly and a sample measuring assembly that are detachably connected to the shielding protective cover; the sampling assembly includes a sampling bottle; a valve connected to one mouth of the sampling bottle through a pipeline; a second valve connected to the other mouth of the sampling bottle through a pipeline; a first quick female connector connected with the first valve through a pipeline; a second quick female connector connected to the second valve through a pipeline; a balance pipeline, one end being connected to the pipeline between the first valve and the first quick female connector, and the other end being connected to the pipeline between the second valve and the second quick female connector.

A device for measuring a total gas content of a primary circuit of a PWR nuclear power plant includes a shielding protective cover, and a sampling assembly and a sample measuring assembly that are detachably connected to the shielding protective cover; the sampling assembly includes a sampling bottle; a valve connected to one mouth of the sampling bottle through a pipeline; a second valve connected to the other mouth of the sampling bottle through a pipeline; a first quick female connector connected with the first valve through a pipeline; a second quick female connector connected to the second valve through a pipeline; a balance pipeline, one end being connected to the pipeline between the first valve and the first quick female connector, and the other end being connected to the pipeline between the second valve and the second quick female connector.