9 results about "Dry storage" patented technology

The application discloses a kind of digital fuel physics supervision method and system suitable for heavy water reactor, it is related to nuclear reactor fuel management technical field, system includes data acquisition module, document scale calculation interface, system management module and central processing module, central processing module configuration basic data, new fuel, FCO, spent fuel, dry storage area management unit.Method is standardized by data acquisition, whole-process digital control, dynamic monitoring and tracing three steps, realize fuel full life cycle closed-loop management.System adopts PDA to cooperate bar code / RFID to realize entity information acquisition and offline synchronization, constructs hierarchical correlation model, with new fuel isolation control, FCO closed-loop approval, spent fuel transfer verification, fine authority control and other functions, can improve management efficiency, reduce human error, strengthen data tracing and operation standardization, guarantee nuclear safety, provide support for management decision, suitable for heavy water reactor fuel physics supervision and whole-process management.

The application provides a kind of nuclear power plant dry storage spent fuel emergency evaluation method, system, equipment and medium, applied to dry nuclear horizontal modular storage system, the dry nuclear horizontal modular storage system includes concrete module and storage container, the method comprises: obtaining the information of natural disaster;According to the type and risk parameter of the natural disaster information of the natural disaster;In response to the risk parameter being higher than the response threshold, the radiation dose of the concrete module is obtained;According to the radiation dose, the effective multiplication coefficient of the storage container is obtained;In response to the effective multiplication coefficient being higher than the effective multiplication coefficient threshold, the storage container transfer operation is executed, can be integrated together by natural disaster risk assessment, radiation dose monitoring and effective multiplication coefficient control, form a complete emergency evaluation and response system, improve the overall efficiency of nuclear power plant in response to disaster.

This invention discloses a tiered drying and storage device for carbon black granulation and its usage method, relating to the field of carbon black granulation and storage technology. The invention designs a load-reducing, large-capacity tiered drying and storage device for carbon black granulation, mainly comprising a partition assembly, a feeding component, a flow meter, lifting rods and sealing devices, a partition rotation drive assembly, and an expansion joint. This invention allows an appropriate amount of carbon black granules to be injected into each storage chamber. A lifting rod with a tension spring is designed on the storage box, and multiple sealing devices are configured on the lifting rod. During discharge from the storage box, the lifting rod is pressed down in a tiered manner, causing the carbon black granules to be discharged layer by layer from low to high within the storage box. This enables a single storage box to continuously handle a large volume of storage and discharge, avoiding significant breakage of the carbon black granules during storage and transportation, and ensuring the efficiency of the carbon black granule storage and discharge process.

The present application relates to the technical field of spent fuel storage, and discloses a spent fuel dry storage vault, which comprises a top air inlet vertical shaft for introducing natural ventilation, a bottom air chamber in communication with the air inlet vertical shaft, a storage chamber above the bottom air chamber, a plurality of shafts arranged in the storage chamber in a vertical direction, a heat generating body sleeved in the shafts in a spaced manner, an annular gap formed between the shafts and the heat generating body, the heat generating body containing spent fuel, the bottom air chamber in communication with a top air chamber through the annular gap, and an air outlet vertical shaft in communication with the top air chamber. Air for natural ventilation enters the air inlet vertical shaft through an air inlet, then enters the bottom air chamber, and then flows into the annular gap and the top air chamber, and is discharged from an air outlet through the air outlet vertical shaft, so that the flow path of the internal air is optimized, the storage chamber enhances the ventilation efficiency and heat exchange performance in a combined manner of heat conduction, convection and radiation heat exchange, the decay heat of the spent fuel in the heat generating body is discharged, and the safety and stability of the spent fuel dry storage vault are ensured.

The present disclosure relates to a spent nuclear fuel dry container having internal oxygen and moisture removal functions. The spent nuclear fuel dry container having internal oxygen and moisture removal functions comprises an oxygen and moisture removal apparatus including: an oxygen removal unit capable of removing oxygen contained in the internal space; and a moisture removal unit capable of removing moisture contained in the internal space.

The application discloses a thick-wall SA350Gr.LF3 large forging for a transfer container of a spent fuel dry storage system, which comprises a SA350Gr.LF3 large forging body, and the components contained in the large forging body and the mass percentage content (wt.%) thereof are as follows: C: 0.05%-0.15%; Cr: 0.10-0.20%; Mo: 0.04-0.06%; V: 0.01-0.03%; Nb: 0.01-0.02%; Al: 0.013-0.017%; N: 80-120ppm; Si: 0.20-0.30%; Mn: 0.70-0.80%; Ni: 3.5-3.7%; P≤0.006%; S≤0.003%; and the balance is Fe. The application further discloses a manufacturing process of the large forging, and the low-temperature toughness of the SA350Gr.LF3 large forging can be improved.

The invention discloses a preparation method of an aluminum-based boron carbide composite material. The aluminum-based boron carbide composite material is composed of boron carbide particles, an aluminum matrix, a nano reinforcement and a coherent interface formed by the nano reinforcement and the matrix. The boron carbide particles absorb neutrons, the nanometer reinforcement stabilizes an aluminum matrix structure, good room-temperature and high-temperature mechanical properties are provided, particularly, severe degradation of the strength of the aluminum-based boron carbide composite material in a high-temperature service environment (200-350 DEG C) is avoided, the service life of the material is prolonged, and the reliability of the material is improved. The aluminum-based boron carbide composite material is suitable for application scenes such as spent fuel dry storage and transportation treatment.

The invention relates to the technical field of spent fuel storage, and discloses a spent fuel storage well for a test and a design construction method.The spent fuel storage well for the test is characterized in that an air inlet channel is arranged in the vertical direction, and ventilation is conducted in the air inlet channel from top to bottom; one end of the lower air chamber is communicated with the lower end of the air inlet channel; the upper air chamber is positioned above the lower air chamber; the upper air chamber is communicated with an exhaust channel which is vertically arranged; the storage chamber is positioned between the upper air chamber and the lower air chamber; the upper air chamber is communicated with the upper end of the storage chamber; the multiple storage unit assemblies are arranged in the storage chamber at intervals and serve as containers for containing the simulated spent fuel. Simulated spent fuel is placed in the storage unit assembly through the spent fuel storage well for testing, and the difficulty of experimental research of a spent fuel dry storage ventilation technology is overcome; the ventilation cooling effect of the whole storage chamber under extreme climates such as windless climates and high-temperature climates can be researched, so that basic test research can be better carried out.

A dry storage systems for radioactive nuclear waste materials may include a double-walled canister system. The canister system may include a canister having a tubular inner shell defining an internal cavity for storing nuclear waste material, a first lid sealably welded to a first end of the inner shell, a primary base plate defining a peripheral edge portion and having an annular closure flange, and an annular full thickness butt weld formed at an abutment joint between the annular closure flange and a second end of the inner shell. The inner shell, first lid, and first end closure may collectively define a sealed primary pressure retention barrier. A tubular outer shell may adjoin the inner shell. The outer shell may be welded to the canister to form a hermetically sealed secondary pressure retention barrier.