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Novel oxide dispersion strengthenedneutron absorption material

A technology of dispersion strengthening and absorbing materials, applied in shielding, nuclear engineering, reactors, etc., can solve the problems of inability to meet long-term high-temperature storage and structural support requirements, low thermal conductivity, poor high-temperature mechanical properties, etc., to simplify design and The effect of manufacturing, high thermal conductivity, high temperature strength improvement

Inactive Publication Date: 2019-05-24
中广核工程有限公司 +2
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0005] However, neutron-absorbing materials are required for spent fuel dry storage containers, and neutron-absorbing materials in the prior art are mainly boron-containing organic matter, boron-aluminum alloys, boron-containing stainless steel, aluminum-based boron carbide materials, etc., which have thermal conductivity Low and high temperature mechanical properties are poor and cannot meet the requirements of long-term high temperature storage and structural support

Method used

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  • Novel oxide dispersion strengthenedneutron absorption material
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  • Novel oxide dispersion strengthenedneutron absorption material

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preparation example Construction

[0055] The present invention also provides a preparation method of a novel oxide dispersion strengthened neutron absorbing material, comprising the following steps:

[0056] 1) Raw material powder mixing: 5-20wt.% of B 4 C. 0.8-5wt.% nanomaterials and powders containing aluminum are uniformly mixed and ball milled;

[0057] 2) Cold isostatic pressing: the uniformly mixed powder is pressed and formed by cold isostatic pressing, and the pressure is maintained to obtain a cold compact;

[0058] 3) Vacuum degassing: place the cold compact in an aluminum sheath for high-temperature vacuum degassing, and seal and weld the cold compact in the aluminum sheath after reaching the required vacuum degree;

[0059] 4) Hot isostatic pressing: use hot isostatic pressing to densify and sinter the vacuum degassed material to obtain a hot compact;

[0060] 5) Shaping the green body: pressing the densified and sintered hot-pressed green body by cold isostatic pressing to obtain the green body;...

Embodiment 1

[0070] 1) Raw material powder mixing: 9wt.% of B 4 C (D97=50μm), 3wt.% nano-Al 2 o 3 materials, and 88wt.% of 1100 aluminum alloy powder were placed in a high-energy ball mill for uniform mixing and ball milling; the ball milling time was 8 hours, and the ball-to-material ratio was 1.5:1;

[0071] 2) Cold isostatic pressing: The uniformly mixed powder is subjected to cold isostatic pressing, and the cold isostatic pressing pressure is 200Mpa, and the pressure is maintained for 10 minutes to obtain a cold compact;

[0072] 3) Vacuum degassing: the cold compact is placed in an aluminum sheath for welding, and the leakage rate after welding is lower than 3×10 -10 Pa·m 3 After / s, vacuumize the package under the condition of 500°C for degassing, and the vacuum degree is not lower than 6×10 -3 Seal and weld the sheath at Pa, preferably, the vacuum degree is not lower than 8×10 -4 Seal the sheath at Pa;

[0073] 4) Hot isostatic pressing: use the hot isostatic pressing process...

Embodiment 2~9

[0079] The preparation methods of Examples 2-9 are basically the same as those of Example 1, except that the components and conditions are different, and the specific parameters are shown in Table 1 and Table 2.

[0080] Table 1 Material composition and preparation conditions of each embodiment

[0081]

[0082]

[0083] Each embodiment preparation condition of table 2

[0084]

[0085] Each embodiment performance test result of table 3

[0086]

[0087] It can be seen from Table 3 that the novel oxide dispersion-strengthened neutron absorbing material prepared by the method of the present invention still has high mechanical properties at high temperature (450° C.), high thermal conductivity and high boron carbide content.

[0088] Compared with the prior art, the novel oxide dispersion-strengthened neutron absorbing material and its preparation method of the present invention have the following technical effects:

[0089] 1) The high-temperature strength of the ...

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Abstract

The invention discloses a novel oxide dispersion strengthenedneutron absorption material. The novel oxide dispersion strengthenedneutron absorption material is prepared from the following materials inpercentage by weight: 5-20% of B4C, 0.8-5% of nano materials, and the balance of powder containing the aluminum element, wherein the nano materials are selected from one or more of nano Al2O3, nano MgO, nano TiO2, nano ZnO, nano ZrO2 and nano rare earth oxides. Compared with the prior art, the novel oxide dispersion strengthenedneutron absorption materialhas high high-temperature intensity, can be used for the neutron absorption function and the structural supporting action at the same time, has a high thermal conductivity coefficient, can be applied to the field of spent fuel storage and transportation, and can greatly reduce the manufacturing cost. In addition, the invention further provides a preparation method of the novel oxide dispersion strengthenedneutron absorption material, theprocess is simple, and the prepared neutron absorption material has the high thermal conductivity coefficient.

Description

technical field [0001] The invention belongs to the field of neutron absorbing materials. More specifically, the invention relates to a novel oxide dispersion strengthened neutron absorbing material and a preparation method thereof. Background technique [0002] Nuclear power plants will produce a certain amount of spent fuel during operation. Since the spent fuel still has certain reactivity, neutron absorbing materials are usually used to absorb the thermal neutrons generated during the decay process to maintain the spent fuel system in a subcritical state. . [0003] Off-reactor intermediate storage is divided into wet storage and dry storage according to the storage method. The former usually builds a spent fuel pool in the factory building, places fuel storage grids in the pool, and cools the spent fuel and controls reactivity through boron-containing water circulation. However, wet storage requires continuous operation and maintenance of the pool cooling system, which...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22C1/05C22C21/00B22F3/04B22F3/15B22F3/18B22F3/24C22C32/00G21F1/08
Inventor 王鑫张鹏程刘彦章庞晓轩王傲松白彬喻应华罗昊杨寿海王伟莫怀森
Owner 中广核工程有限公司
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