Neutron shielding material for spent fuel shipping flask

Abstract

The invention relates to a neutron shielding material for a spent fuel shipping flask. The neutron shielding material is prepared from epoxy resin, a curing agent, a flame retardant and a boron compound, wherein epoxy resin consists of 35-75 wt% of bisphenol A epoxy resin or bisphenol F epoxy resin, 5-40 wt% of hydrogenated epoxy resin and 20-40 wt% of an active diluent; the curing agent is a polyamine compound, and the consumption of the curing agent is calculated according to the condition that the equivalence ratio of amine hydrogen to epoxy group is 0.8-1.1; the flame retardant is one or two of zinc borate, antimony oxide, magnesium hydroxide or aluminium hydroxide, and weight ratio of the consumption of the flame retardant to the total consumption of epoxy resin and the curing agent is 1.1-1.7; the boron compound is boron carbide or boron nitride, and the consumption of the boron compound is 0.1-10 wt% of the total weight of epoxy resin, the curing agent and the flame retardant. The neutron shielding material has the viscosity suitable for casting forming, and meets the requirements on material homogeneity, density, neutron shielding capability and other properties of the spent fuel shipping flask.

Description

technical field [0001] The invention relates to a neutron shielding material for a spent fuel transport container. Further, it relates to potting materials suitable for use as spent nuclear fuel transport containers. Background technique [0002] The so-called spent fuel refers to the medium and low radioactive nuclear waste produced during the operation of nuclear power plants. According to my country's medium and long-term development plan for nuclear power, by 2020, the operating installed capacity of nuclear power will strive to reach 40 million kilowatts, and 18 million kilowatts are under construction. At the same time as the construction of nuclear power projects, a disposal site for medium and low-level radioactive nuclear waste must be built simultaneously, and the safe transportation of spent fuel to the disposal site is one of the important issues that must be solved in the development of nuclear power. The key equipment for spent fuel transportation is the tran...

AI Technical Summary

Problems solved by technology

In addition, limited by the structure of the spent fuel transport container, the neutron shielding material required for the transport container usually needs to be molded by casting, so the neutron shielding material must have a low viscosity to ensure the compactness of the neutron shielding material during the casting process , the uniformity of various raw materials, especially boron, otherwise it will affect the shielding effect

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