Abstract: A nuclear reactor main heat and waste heat integrated thermal exchanger has a first coolant zone for a first main heat loop, a second coolant zone for a second main heat loop and a third coolant zone for a waste heat removal loop. The first coolant for the first main heat loop passes through the first coolant inlet, and then reaches the orifice plate, and finally flows out from the first coolant outlet. The second coolant for the second main heat loop passes through the second coolant inlet, and then reaches the lower tube sheet, and finally flows out from the second coolant outlet. The third coolant for the waste heat removal loop enters the entrance sleeve through the third coolant inlet, and then enters multiple tubes of the tube bundle, and then enters the exit sleeve, and finally flows out from the third coolant outlet.

Abstract: 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.

Abstract: An experimental system a method for studying jet impact characteristics at a core outlet of a fast reactor are provided. The system includes a jet impact main loop including a water storage tank, plunger pumps, a filter, preheaters, a jet impact chamber, a heat regenerator, a condenser, valves, flow meters and pipelines connecting these facilities; a cooling loop including cooling tower, a cooling pump, a regulating valve and a flow meter; and a makeup water loop including a deionized water machine, a makeup water tank and a plunger pump. Water in the water storage tank flows to the heat regenerator via the plunger pump, is preliminarily heated by the heat regenerator and then is divided into three branches to flow to the jet impact container.

Abstract: The present disclosure relates to a narrow slit channel visualization experimental device and method under a six-degree-of-freedom motion condition. The system comprises a six-degree-of-freedom motion simulation platform, a main circulation loop, a cooling water system, an electric heating system and a bubble monitoring system, wherein the main circulation loop is composed of an S-shaped preheater, a three-surface visualization experimental section, a double-pipe condenser, a pressurizing circulating pump, a voltage stabilizer and related equipment, wherein the cooling water system is composed of the double-pipe condenser, a plate heat exchanger, a cooling tower, a cooling fan, a cooling water tank and related equipment, wherein the electric heating system is composed of a direct-current power supply, a low-voltage power controller and a transformer, and wherein the bubble monitoring system is composed of two high-speed cameras, a PIV measuring system and an electric servo module.

Abstract: A multipurpose passive residual heat removal system for a small fluoride-salt-cooled high-temperature reactor is provided, including: a circulation loop composed of a reactor body system, a multipurpose passive residual heat removal system, pipes and other connecting equipment between each system; wherein the reactor body system serves as the heat source of the system, using helical cruciform fuel element and FLiBe molten salt coolant, wherein a thermal power is 125 MW, and a temperature of the core outlet reaches 700° C., which has the advantages of high-temperature and low-pressure operation, inherent safety and compact structure. The multipurpose passive residual heat removal system not only serves as a special safety facility to ensure the passive safety of the reactor, but also efficiently recovers and utilizes the residual heat through the thermoelectric power generation device for power generation.

Abstract: A method for analyzing a sever accident in a nuclear reactor based on an advanced particle method includes steps of: 1) performing geometric modeling, setting initial conditions and boundary conditions; 2) updating material physical properties and key parameters; 3) performing mechanical structure module calculation, updating solid particle stress, strain, internal energy, displacement and velocity; 4) performing thermal hydraulic module calculation, updating fluid particle internal energy, position and velocity; 5) performing chemical reaction module calculation, updating particle matter composition and internal energy; 6) performing neutron physics module calculation, updating particle neutron flux density; and 7) outputting data. The method of the present invention is based on the discrete form of the advanced particle method, which is capable of accurately capturing cross-sectional changes, matter changes, and phase changes.

Abstract: The present disclosure discloses a wind-solar reactor system and a working method thereof. The wind-solar reactor system comprises a nuclear reactor system, a wind power generation system, a solar power storage system and a balance energy system, wherein the nuclear reactor system uses an integrated small modular reactor design, the solar power storage system uses a tower-type solar power storage system design, and a hydrogen production system uses a copper-chlorine cycle hydrogen production technology. A reactor keeps rated full-power operation, generated electricity is adjusted and distributed through a power controller, most of the electricity is used for smoothing the fluctuation of wind power generation, and the excess electricity is used for hydrogen storage of the hydrogen system. Solar power is used for heating saturated steam generated by the reactor into superheated steam through a heater, and then the superheated steam enters a high-pressure cylinder to do work by expansion.

Abstract: Disclosed are a test loop for simulating a steam generator with or without an axial economizer and a test method thereof. The loop includes a cooling water loop, a water supply loop, a recirculated water loop and a power supply. The cooling water loop is used for condensing and cooling wet steam and providing the wet steam to the water supply loop and the recirculated water loop. The water supply loop is used for providing cold-state water supply for a test device, the recirculated water loop is used for reheating cooled water to be saturated and providing the water to the test device. The power supply is used for supplying power to heating equipment and an electric heater in the test device. The present disclosure provides a test method of the loop. Simulation tests can be carried out on a steam generator with or without an axial economizer.

Abstract: A combined power generation system and method of a small fluoride-salt-cooled high-temperature reactor and solar tower is provided, which belongs to the field of new energy and renewable energy application and includes: a nuclear reactor power generation system, a solar tower power generation system and a heat compensation system. Both the nuclear reactor power generation system and the solar tower power generation system adopt supercritical carbon dioxide Brayton cycle system to generate electricity efficiently; molten salt pool in the nuclear reactor power generation system stores high-temperature heat from the modular reactor, and multi-stage temperature heat is utilized for generating power and compensating heat required by the solar tower power generation system.

Abstract: A multipurpose small modular fluoride-salt-cooled high-temperature reactor energy system includes: a reactor body system, a passive residual heat removal system, a compact supercritical carbon dioxide Brayton cycle system, a secondary loop system, and a comprehensive utilization supercritical carbon dioxide Brayton cycle system. Nuclear reactor adopts helical cruciform fuel and graphite matrix material filled with TRISO element, which can improve heat transfer performance and inherent safety. Thermal efficiency of the compact supercritical carbon dioxide Brayton cycle system is above 48%, which can be used in places with limited space. Thermal efficiency of the comprehensive utilization supercritical carbon dioxide Brayton cycle system is above 54%, which can be applied to places with abundant resources. The present invention not only realizes efficient and compact utilization of energy, but also meets the needs of multiple purposes, integrated production, storage and conversion of energy.

Abstract: A main heat and waste heat integrated thermal exchanger for a small nuclear reactor has a first coolant zone for a first main heat loop, a second coolant zone for a second main heat loop and a third coolant zone for a waste heat removal loop. The first coolant for the first main heat loop passes through the first coolant inlet, and then reaches the orifice plate, and finally flows out from the first coolant outlet. The second coolant for the second main heat loop passes through the second coolant inlet, and then reaches the lower tube sheet, and finally flows out from the second coolant outlet. The third coolant for the waste heat removal loop enters the entrance sleeve through the third coolant inlet, and then enters multiple tubes of the tube bundle, and then enters the exit sleeve, and finally flows out from the third coolant outlet.

Abstract: The present disclosure relates to a narrow slit channel visualization experimental device and method under a six-degree-of-freedom motion condition. The system comprises a six-degree-of-freedom motion simulation platform, a main circulation loop, a cooling water system, an electric heating system and a bubble monitoring system, wherein the main circulation loop is composed of an S-shaped preheater, a three-surface visualization experimental section, a double-pipe condenser, a pressurizing circulating pump, a voltage stabilizer and related equipment, wherein the cooling water system is composed of the double-pipe condenser, a plate heat exchanger, a cooling tower, a cooling fan, a cooling water tank and related equipment, wherein the electric heating system is composed of a direct-current power supply, a low-voltage power controller and a transformer, and wherein the bubble monitoring system is composed of two high-speed cameras, a PIV measuring system and an electric servo module.

Abstract: An experimental system a method for studying jet impact characteristics at a core outlet of a fast reactor are provided. The system includes a jet impact main loop including a water storage tank, plunger pumps, a filter, preheaters, a jet impact chamber, a heat regenerator, a condenser, valves, flow meters and pipelines connecting these facilities; a cooling loop including cooling tower, a cooling pump, a regulating valve and a flow meter; and a makeup water loop including a deionized water machine, a makeup water tank and a plunger pump. Water in the water storage tank flows to the heat regenerator via the plunger pump, is preliminarily heated by the heat regenerator and then is divided into three branches to flow to the jet impact container.

Abstract: Disclosed are a test loop for simulating a steam generator with or without an axial economizer and a test method thereof. The loop includes a cooling water loop, a water supply loop, a recirculated water loop and a power supply. The cooling water loop is used for condensing and cooling wet steam and providing the wet steam to the water supply loop and the recirculated water loop. The water supply loop is used for providing cold-state water supply for a test device, the recirculated water loop is used for reheating cooled water to be saturated and providing the water to the test device. The power supply is used for supplying power to heating equipment and an electric heater in the test device. The present disclosure provides a test method of the loop. Simulation tests can be carried out on a steam generator with or without an axial economizer.

Abstract: 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.

Abstract: The present disclosure discloses a wind-solar reactor system and a working method thereof. The wind-solar reactor system comprises a nuclear reactor system, a wind power generation system, a solar power storage system and a balance energy system, wherein the nuclear reactor system uses an integrated small modular reactor design, the solar power storage system uses a tower-type solar power storage system design, and a hydrogen production system uses a copper-chlorine cycle hydrogen production technology. A reactor keeps rated full-power operation, generated electricity is adjusted and distributed through a power controller, most of the electricity is used for smoothing the fluctuation of wind power generation, and the excess electricity is used for hydrogen storage of the hydrogen system. Solar power is used for heating saturated steam generated by the reactor into superheated steam through a heater, and then the superheated steam enters a high-pressure cylinder to do work by expansion.

Abstract: A substrate holding apparatus for semiconductor processing like wire bonding process is disclosed. Two or more holding points at both side of center locating point are provided to created a distributed holding force at clamp tool holding shoulder to generate a moment about substrate moving direction to act on clamp tool so that clamp tool can clamp on substrate more evenly at all sides for better process quality.