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Method for preparing B4C-Al neutron-absorbing plate for spent fuel storage and transportation

A neutron absorbing plate and spent fuel technology, applied in the manufacture of reactors, reactors, reducing greenhouse gases, etc., can solve the problems of complex process, high cost, high content of iron and other impurities, and achieve the effect of overcoming interface reactions

Active Publication Date: 2013-01-23
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

This kind of boron carbide-aluminum composite material prepared by high-energy ball milling and hot pressing has high content of impurities such as iron, complicated process and high cost.

Method used

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Examples

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Effect test

preparation example Construction

[0016] Spent fuel storage application B of the present invention 4 The preparation method of C-Al neutron absorbing plate, concrete steps are as follows:

[0017] 1. Mixing ingredients: B 4 C and pure Al powder or Al alloy powder with an average particle size of 20 μm to 100 μm and a mass fraction of 35% to 90% are uniformly mixed in a mixer;

[0018] 2. Core billet pressing: put the above-mentioned mixture in the mold, mold it into a dense core billet under 200MPa ~ 450MPa, and press in an inert atmosphere or a vacuum degree of 10 -1 ~10 -4 Sintering in a vacuum furnace below Pa, the sintering temperature is 380 ° C ~ 650 ° C;

[0019] 3. Rolling into plate: the sintered B 4 The C and Al composite material core is welded and packaged with pure aluminum or aluminum alloy frame, and then hot rolled to the designed size at a temperature of 380°C to 600°C, cooled to room temperature, then cold rolled and straightened to the final size to obtain B 4 C-Al neutron absorbing pla...

Embodiment 1

[0022] 1. Mixing ingredients: B with an average particle size of 100 μm and a mass fraction of 10% 4 C particles and Al powder with an average particle size of 60 μm and a mass fraction of 90% are uniformly mixed in a mixer;

[0023] 2. Core billet pressing: put the above mixed material in a mold, mold it into a dense core billet at 200MPa, and sinter in an inert atmosphere at a sintering temperature of 380°C;

[0024] 3. Rolling into plates: Weld and package the sintered dense core billet with pure aluminum or aluminum alloy frame, then hot rolling, the hot rolling temperature is 600°C, after cooling to room temperature, then cold rolling and straightening to the final size, to obtain 4000mm x 200mm x 1.9mm B 4 C-Al neutron absorbing plate.

Embodiment 2

[0026] 1. Mixing ingredients: B with an average particle size of 35 μm and a mass fraction of 26% 4 C particles and Al powder with an average particle size of 60 μm and a mass fraction of 74% are uniformly mixed in a mixer;

[0027] 2. Core billet pressing: put the above mixed material in a mold, press it into a dense core billet at 280MPa, and sinter it in a vacuum furnace with a vacuum degree of 4.5×10 -2 Pa, the sintering temperature is 500°C;

[0028] 3. Rolling into plates: Weld and package the sintered dense core billet with pure aluminum or aluminum alloy frame, then hot rolling, the hot rolling temperature is 500°C, after cooling to room temperature, then cold rolling and straightening to the final size, to obtain 4000m × 200mm × 2.0mm B 4 C-Al neutron absorbing plate.

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PUM

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Abstract

The invention discloses a method for preparing a B4C-Al neutron-absorbing plate for spent fuel storage and transportation, which is implemented by adopting a frame rolling technique through the following steps: firstly, uniformly mixing a certain amount of B4C powder and Al matrix powder; then, carrying out mould pressing on the obtained mixture so as to obtain a compact green core body, sintering the compact green core body in a vacuum furnace, putting the sintered core body into an aluminum alloy frame, and sealing the aluminum alloy frame; and finally, rolling to obtain a plate. The process for preparing the neutron-absorbing plate is simple, the B4C is uniformly distributed into an Al matrix, and the B4C and the Al matrix have a good interfacial bond. The neutron-absorbing plate prepared by using the method disclosed by the invention is suitable for being used as a neutron-absorbing material in spent fuel tanks and transportation containers, thereby controlling the critical safetyof the spent fuel.

Description

technical field [0001] The invention relates to a preparation method for a nuclear reactor highly radioactive spent fuel processing facility, in particular to a spent fuel storage application B 4 A preparation method of a C-Al neutron absorbing plate. Background technique [0002] During the storage and transportation of highly radioactive spent fuel from nuclear reactors, neutron absorbing materials are important materials to ensure safety. It absorbs neutrons released from spent fuel, maintains the spent fuel in a subcritical state, and prevents the release of radioactive materials to the environment. Boron has the highest neutron absorption cross-section among all neutron-absorbing elements. When selecting a neutron absorber, boron-containing compounds become a priority, and boron carbide (B 4 C) It has physical and chemical properties such as high melting point, high strength, low density, small thermal expansion coefficient, good thermal conductivity, stable structur...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G21C21/00
CPCY02E30/30
Inventor 邹从沛刘晓珍龙冲生周荣生孙长龙刘超红王录全李刚简敏杨勇飞易伟王美玲付道贵王贯春刘云明
Owner NUCLEAR POWER INSTITUTE OF CHINA
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