A kind of preparation method of neutron absorbing composite material
A technology that absorbs composite materials and neutrons, applied in shielding, nuclear engineering, reactors, etc., can solve the problems of difficult protection, poor anti-corrosion performance, and low strength, and achieve good compactness, accurate and detailed data, and proportioning reasonable effect
Active Publication Date: 2018-02-23
TAIYUAN UNIV OF TECH
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Problems solved by technology
[0004] How to prevent nuclear fuel rods and spent fuel rods from emitting neutrons is a technical problem. Neutron absorbing materials must be used to make neutron absorbing plates for protection; most of the current neutron absorbing materials have low strength, low hardness, and corrosion resistance. Poor performance, it is difficult to achieve the purpose of protection
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Embodiment Construction
[0055] The present invention will be further described below in conjunction with accompanying drawing:
[0056] figure 1 As shown in the figure, it is the vacuum hot pressing sintering state diagram of the neutron absorbing composite material. The position and connection relationship of each part should be correct, and the proportion should be adjusted according to the quantity, and the operation should be carried out in sequence.
[0057] Quantities of the chemical substances used in the preparation are determined according to a preset range, with grams, milliliters, and millimeters as measurement units.
[0058] The vacuum hot-pressing sintering furnace is a vertical rectangle, the bottom of the vacuum hot-pressing sintering furnace 1 is a furnace seat 2, the upper part is a furnace cover 3, and the inside is a furnace chamber 29; on the inner wall of the vacuum sintering furnace 1 is a plasma discharge heater 7; The outside of the vacuum hot-pressing sintering furnace 1 is...
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Abstract
The invention relates to a preparation method of a neutron absorbing composite material and aims to solve the problems of poor neutron absorption function, low strength, low hardness and poor corrosion resistance of a nuclear protection material. According to the preparation method, boron carbide powder, titanium powder, titanium diboride powder and samarium powder are taken as raw materials and a titanium-nickel wire is taken as a toughening material to prepare a neutron absorbing composite material block body by steps of material preparation, ball milling, die filling, plasma discharge heating and vacuum hot-pressed sintering. The preparation method is advanced in process, reasonable in proportion and precise and accurate in data; the metallographic structure of the neutron absorbing composite material block body is good in compactness; the titanium-nickel wire is spirally hot-pressed inside a metallographic body, so the tensile strength is enhanced, the hardness is as high as 400 HV, the neutron absorption rate is 95%, and the nuclear protection performance of the neutron absorbing composite material is increased by 97% in comparison with that of an existing material, so the preparation method provided by the invention is an advanced method for preparing the neutron absorbing composite material.
Description
technical field [0001] The invention relates to a preparation method of a neutron-absorbing composite material, which belongs to the technical field of preparation and application of neutron-absorbing and shielding materials. Background technique [0002] Nuclear power is the clean energy with the most development prospects. A nuclear power plant is a nuclear power plant. The materials used are nuclear radioactive substances, which are extremely radioactive, and are extremely harmful to the environment, humans, and animals. [0003] How to carry out nuclear protection and prevent nuclear pollution is a complex research topic. Many kinds of nuclear fuel rods and spent fuel rods are used in nuclear power plants, and there are a large number of them. How to store and transport these nuclear fuel rods and spent fuel rods has become a big problem. , During storage and transportation, neutrons will be emitted outward, and even nuclear fuel rods and spent fuel rods will react inter...
Claims
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IPC IPC(8): C22C47/14C22C49/11C22C49/14C22F1/18G21F1/02C22C111/00
CPCC22C47/14C22C49/11C22C49/14C22F1/183G21F1/02
Inventor 王文先谭敏波张锦文陈洪胜董鹏
Owner TAIYUAN UNIV OF TECH