CN105671373A - Preparing method for neutron absorption plate with high B4C content - Google Patents

Preparing method for neutron absorption plate with high B4C content Download PDF

Info

Publication number
CN105671373A
CN105671373A CN201610141574.XA CN201610141574A CN105671373A CN 105671373 A CN105671373 A CN 105671373A CN 201610141574 A CN201610141574 A CN 201610141574A CN 105671373 A CN105671373 A CN 105671373A
Authority
CN
China
Prior art keywords
powder
sintering
blank
carried out
content
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN201610141574.XA
Other languages
Chinese (zh)
Inventor
程晓农
吕鹏
王显明
马云涛
冉波
王志伟
唐小存
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
JIANGSU ENTC NUCLEAR TECHNOLOGY JOINT STOCK Co Ltd
Jiangsu University
Original Assignee
JIANGSU ENTC NUCLEAR TECHNOLOGY JOINT STOCK Co Ltd
Jiangsu University
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by JIANGSU ENTC NUCLEAR TECHNOLOGY JOINT STOCK Co Ltd, Jiangsu University filed Critical JIANGSU ENTC NUCLEAR TECHNOLOGY JOINT STOCK Co Ltd
Priority to CN201610141574.XA priority Critical patent/CN105671373A/en
Publication of CN105671373A publication Critical patent/CN105671373A/en
Pending legal-status Critical Current

Links

Classifications

    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C21/00Alloys based on aluminium
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B22CASTING; POWDER METALLURGY
    • B22FWORKING METALLIC POWDER; MANUFACTURE OF ARTICLES FROM METALLIC POWDER; MAKING METALLIC POWDER; APPARATUS OR DEVICES SPECIALLY ADAPTED FOR METALLIC POWDER
    • B22F3/00Manufacture of workpieces or articles from metallic powder characterised by the manner of compacting or sintering; Apparatus specially adapted therefor ; Presses and furnaces
    • B22F3/12Both compacting and sintering
    • B22F3/16Both compacting and sintering in successive or repeated steps
    • BPERFORMING OPERATIONS; TRANSPORTING
    • B22CASTING; POWDER METALLURGY
    • B22FWORKING METALLIC POWDER; MANUFACTURE OF ARTICLES FROM METALLIC POWDER; MAKING METALLIC POWDER; APPARATUS OR DEVICES SPECIALLY ADAPTED FOR METALLIC POWDER
    • B22F3/00Manufacture of workpieces or articles from metallic powder characterised by the manner of compacting or sintering; Apparatus specially adapted therefor ; Presses and furnaces
    • B22F3/12Both compacting and sintering
    • B22F3/16Both compacting and sintering in successive or repeated steps
    • B22F3/162Machining, working after consolidation
    • CCHEMISTRY; METALLURGY
    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22CALLOYS
    • C22C32/00Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ
    • C22C32/0047Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ with carbides, nitrides, borides or silicides as the main non-metallic constituents
    • C22C32/0052Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ with carbides, nitrides, borides or silicides as the main non-metallic constituents only carbides
    • C22C32/0057Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ with carbides, nitrides, borides or silicides as the main non-metallic constituents only carbides based on B4C
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F1/00Shielding characterised by the composition of the materials
    • G21F1/02Selection of uniform shielding materials
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F3/00Shielding characterised by its physical form, e.g. granules, or shape of the material

Abstract

The invention belongs to the field of preparation of neutron absorption materials used for storing nuclear reaction spent fuel, and particularly relates to a preparing method for a neutron absorption plate with the high B4C content. By means of the preparing method, according to a preset chemical proportion, Al alloy powder and B4C powder which are higher in granularity are evenly mixed, then vacuum sintering is carried out, hot rolling is carried out, annealing treatment is carried out after the size in a reserved scheme is obtained through rolling, and the high-B4C-content neutron absorption plate with the density capable of reaching 99.2% is prepared.

Description

One has high B4The preparation method of C content neutron absorber plate
Technical field
The invention belongs to the neutron absorber material preparation field for storing nuclear reaction spentnuclear fuel, particularly relate to one and there is high B4The preparation method of C content neutron absorber plate.
Background technology
Nuclear power is following low-carbon electric power " fresh combatants ", but owing to nuclear spent fuel has the features such as radioactivity is strong, toxicity big, have generation criticality accident dangerous, the therefore storage of spentnuclear fuel, transport and subsequent treatment equipment are one of keys ensureing nuclear power safety in operation. Break through the technical bottleneck of this type of equipment neutron absorber material, be the important leverage effectively facilitating China's nuclear power engineering healthy and rapid development. But before this project implementation, the whole dependence on import of spentnuclear fuel neutron absorber material, this type of material composition and technology of preparing are all blocked by offshore company, and product market is monopolized by it. Therefore the neutron absorber material suitable in the intensive storage screen work of spentnuclear fuel dry and wet and transport containers thereof is produced, for preventing the generation of nuclear safety accident, ensureing the safe operation of nuclear power generating equipment, especially will appreciate that the production technology of entirely autonomous intellectual property and technology, the international competitiveness improving China's nuclear power technology and equipment has very important significance.
B4C/Al neutron absorber material is the current developed country three generations power station intensive storage screen work of spentnuclear fuel dry and wet and the Latest Materials of transport container reactivity control thereof. AAR manufacturing company of the U.S., METAMIC company are all to B4C/Al neutron absorber material has carried out research preparation. B4C/Al can be ratified for spentnuclear fuel wet method bunkerage by U.S.'s core pipe, and the recommended spentnuclear fuel screen work for district of Arkansas State nuclear power plant 1 and 2nd district; In the design in AP1000 spent nuclear fuel in nuclear power plant pond, additionally also use this material as neutron absorber material. But B4The manufacturing process of C/Al neutron absorber material is blocked by foreign vendor as confidential technique. In recent years, the B for the purpose of spentnuclear fuel storing neutron absorber material4The research of C/Al composite is carried out at Chinese Nuclear Power Design Academy, studies the achievement in research achieving independent intellectual property right in proportioning raw materials and casing pine dress rolling mill practice etc. by experiment, but produces from industrialization and also have certain gap. High-performance neutron absorber material as one of the critical component that nuclear-power reactor spentnuclear fuel processes depends on import for a long time always, it has also become the bottleneck that restriction China nuclear industry develops in a healthy way.
Advanced B4C/Al neutron absorption composite material is applied in spentnuclear fuel is piled after reactor core draws off to store, Spent Fuel Pool is stored and the long process such as storage are transported in post processing, belong to the visual plant in nuclear energy fuel recycle industrial chain, it is related to the safety of nuclear industry, cross over the nuclear energy fuel recycle full phase in longevity of 40 years, be one of country's nuclear power Long-and Medium-term Development planning production domesticization subject content.It is not only Construction of Nuclear Electricity, dual-use naval vessel, the offer nuclear safety guarantee of nucleon research device, also will drive and support that fuel post processing is domesticized simultaneously, and have irreplaceable effect, wide market.
Summary of the invention
The predetermined stoicheiometry of present invention is by Al alloy powder thinner for granularity and B4After C powder mix homogeneously, vacuum-sintering, carry out hot rolling, after being rolling to predetermined scheme size, be annealed processing, make density and can reach the high B of 99.2%4The neutron absorber plate of C content.
The technical solution used in the present invention is as follows:
1. mixed powder: be the B of 20-50 μm by Al alloy powder and average particle size that average particle size is 40-55 μm4C powder, according to the ratio of mass percent 90-35%:10-65%, by two kinds of powder body mix homogeneously in batch mixer.
2. binder: by the powder of mix homogeneously, loads in isostatic pressing machine, and press temperature is at 20-80 DEG C, and pressure is 100-400MPa.
3. vacuum degassing sintering: the blank after isostatic pressed is placed in vacuum drying oven and carried out vacuum degassing sintering, and vacuum is maintained at 10-2-10-3Pa, sintering temperature is 300-440 DEG C, and sintering time is 5-15 hour.
4. hot rolling: the blank after sintering is carried out multi-pass rolling at 300-440 DEG C, and drafts is every time 10-40%, until being rolled to the sheet material of predetermined thickness by blank.
5. annealing: be annealed the sheet material of hot rolling processing, make neutron absorber material.
The present invention is by Al alloy powder thinner for granularity and B4After C powder mix homogeneously, putting in high pressure isostatic pressing machine, utilize the incompressible character of medium and uniformly transfer the character of pressure, from all directions, sample is carried out uniform pressurization, now its pressure size is constant and be delivered evenly to all directions. Therefore the pressure experienced in all directions of the powder body in high-pressure bottle is uniform and of the same size. By these means, not only increase Al alloy powder and B4The uniformity of C powder, and greatly reduce sintering temperature. The present invention makes density can reach the high B of 99.2%4The neutron absorber plate of C content. Preparation technology is simple, by reducing powder particle size and the method utilizing isostatic pressing, reduces reaction temperature, shortens sintering time, and equipment requirements is not high, and energy consumption is relatively low, and the neutron absorber plate of preparation is homogeneous, B4C content is high, stable performance, can be used as the neutron absorber material in spentnuclear fuel storage facility after nuclear reaction.
Accompanying drawing explanation
Fig. 1 is the metallograph of neutron absorber material.
Fig. 2 is that middle daughter board density is with isostatic pressed pressure change curve.
Fig. 3 is that neutron absorption rate is with isostatic pressed pressure change curve.
Detailed description of the invention
Understanding the present invention in order to clearer, below in conjunction with embodiment, the present invention is described in further detail.
Embodiment one
Prepared by middle daughter board:
1. mixed powder: by the B that Al alloy powder and average particle size are 25 μm that average particle size is 45 μm4C powder, according to the ratio of mass percent 80%:20%, by two kinds of powder body mix homogeneously in batch mixer.
2. binder: by the powder of mix homogeneously, loads in isostatic pressing machine, and press temperature 40 DEG C, pressure is 180Mpa.
3. vacuum degassing sintering: the blank after isostatic pressed is placed in vacuum drying oven and carried out vacuum degassing sintering, and vacuum is maintained at 10-2-10-3Pa, sintering temperature is 300 DEG C, and sintering time is 8 hours.
4. hot rolling: the blank after sintering is carried out multi-pass rolling at 300 DEG C, drafts be every time 20%, until the sheet material that blank is rolled to predetermined thickness;
5. annealing: be annealed the sheet material of hot rolling processing.
Pattern and performance detection:
1. adopting Archimedes's drainage that composite is carried out density measurement, density is 94.3%;
2. the metallographic structure utilizing optical microscope centering daughter board is observed;
3. the neutron utilizing China Engineering Physics Research Institute accelerates to carry out neutron absorption rate test on irradiation test machine, and neutron absorption rate is 89%.
Embodiment two
Prepared by middle daughter board:
1. mixed powder: by the B that Al alloy powder and average particle size are 20 μm that average particle size is 40 μm4C powder, according to the ratio of mass percent 68%:32%, by two kinds of powder body mix homogeneously in batch mixer.
2. binder: by the powder of mix homogeneously, loads in isostatic pressing machine, and press temperature 80 DEG C, pressure is 205MPa.
3. vacuum degassing sintering: the blank after isostatic pressed is placed in vacuum drying oven and carried out vacuum degassing sintering, and vacuum is maintained at 10-2-10-3Pa, sintering temperature is 350 DEG C, and sintering time is 10 hours.
4. hot rolling: the blank after sintering is carried out multi-pass rolling at 350 DEG C, drafts be every time 25%, until the sheet material that blank is rolled to predetermined thickness.
5. annealing: be annealed the sheet material of hot rolling processing.
Pattern and performance detection:
1. adopting Archimedes's drainage that composite is carried out density measurement, density is 99.2%.
2. the metallographic structure utilizing optical microscope centering daughter board is observed.
3. the neutron utilizing China Engineering Physics Research Institute accelerates to carry out neutron absorption rate test on irradiation test machine, and neutron absorption rate is 93%.
Embodiment three
Prepared by middle daughter board:
1. mixed powder: by the B that Al alloy powder and average particle size are 20 μm that average particle size is 40 μm4C powder, according to the ratio of mass percent 68%:32%, by two kinds of powder body mix homogeneously in batch mixer.
2. binder: by the powder of mix homogeneously, loads in isostatic pressing machine, and press temperature 80 DEG C, pressure is 100MPa.
3. vacuum degassing sintering: the blank after isostatic pressed is placed in vacuum drying oven and carried out vacuum degassing sintering, and vacuum is maintained at 10-2-10-3Pa, sintering temperature is 350 DEG C, and sintering time is 10 hours.
4. hot rolling: the blank after sintering is carried out multi-pass rolling at 350 DEG C, drafts be every time 25%, until the sheet material that blank is rolled to predetermined thickness.
5. annealing: be annealed the sheet material of hot rolling processing.
Pattern and performance detection:
4. adopting Archimedes's drainage that composite is carried out density measurement, density is 82.5%.
5. the metallographic structure utilizing optical microscope centering daughter board is observed.
6. the neutron utilizing China Engineering Physics Research Institute accelerates to carry out neutron absorption rate test on irradiation test machine, and neutron absorption rate is 84%.
Embodiment four
Prepared by middle daughter board:
1. mixed powder: by the B that Al alloy powder and average particle size are 20 μm that average particle size is 40 μm4C powder, according to the ratio of mass percent 68%:32%, by two kinds of powder body mix homogeneously in batch mixer.
2. binder: by the powder of mix homogeneously, loads in isostatic pressing machine, and press temperature 80 DEG C, pressure is 400MPa.
3. vacuum degassing sintering: the blank after isostatic pressed is placed in vacuum drying oven and carried out vacuum degassing sintering, and vacuum is maintained at 10-2-10-3Pa, sintering temperature is 350 DEG C, and sintering time is 10 hours.
4. hot rolling: the blank after sintering is carried out multi-pass rolling at 350 DEG C, drafts be every time 25%, until the sheet material that blank is rolled to predetermined thickness.
5. annealing: be annealed the sheet material of hot rolling processing.
Pattern and performance detection:
4. adopting Archimedes's drainage that composite is carried out density measurement, density is 81.5%.
8. the metallographic structure utilizing optical microscope centering daughter board is observed.
9. the neutron utilizing China Engineering Physics Research Institute accelerates to carry out neutron absorption rate test on irradiation test machine, and neutron absorption rate is 80.9%.
Embodiment five
Prepared by middle daughter board:
1. mixed powder: by the B that Al alloy powder and average particle size are 45 μm that average particle size is 45 μm4C powder, according to the ratio of mass percent 55%:45%, by two kinds of powder body mix homogeneously in batch mixer.
2. binder: by the powder of mix homogeneously, loads in isostatic pressing machine, and press temperature 80 DEG C, pressure is 300MPa.
3. vacuum degassing sintering: the blank after isostatic pressed is placed in vacuum drying oven and carried out vacuum degassing sintering, and vacuum is maintained at 10-2-10-3Pa, sintering temperature is 400 DEG C, and sintering time is 6 hours.
4. hot rolling: the blank after sintering is carried out multi-pass rolling at 400 DEG C, drafts be every time 30%, until the sheet material that blank is rolled to predetermined thickness.
5. annealing: be annealed the sheet material of hot rolling processing.
Pattern and performance detection:
1. adopting Archimedes's drainage that composite is carried out density measurement, density is 90.4%;
2. the metallographic structure utilizing optical microscope centering daughter board is observed.
3. the neutron utilizing China Engineering Physics Research Institute accelerates to carry out neutron absorption rate test on irradiation test machine, and neutron absorption rate is 91%.
Embodiment six
Prepared by middle daughter board:
1. mixed powder: by the B that Al alloy powder and average particle size are 45 μm that average particle size is 45 μm4C powder, according to the ratio of mass percent 55%:45%, by two kinds of powder body mix homogeneously in batch mixer.
2. binder: by the powder of mix homogeneously, loads in isostatic pressing machine, and press temperature 100 DEG C, pressure is 300MPa.
3. vacuum degassing sintering: the blank after isostatic pressed is placed in vacuum drying oven and carried out vacuum degassing sintering, and vacuum is maintained at 10-2-10-3Pa, sintering temperature is 400 DEG C, and sintering time is 6 hours.
4. hot rolling: the blank after sintering is carried out multi-pass rolling at 400 DEG C, drafts be every time 30%, until the sheet material that blank is rolled to predetermined thickness.
5. annealing: be annealed the sheet material of hot rolling processing.
Pattern and performance detection:
4. adopting Archimedes's drainage that composite is carried out density measurement, density is 82.4%;
5. the metallographic structure utilizing optical microscope centering daughter board is observed.
6. the neutron utilizing China Engineering Physics Research Institute accelerates to carry out neutron absorption rate test on irradiation test machine, and neutron absorption rate is 85.4%.
Embodiment seven
Prepared by middle daughter board:
1. mixed powder: by the B that Al alloy powder and average particle size are 45 μm that average particle size is 45 μm4C powder, according to the ratio of mass percent 55%:45%, by two kinds of powder body mix homogeneously in batch mixer.
2. binder: by the powder of mix homogeneously, loads in isostatic pressing machine, and press temperature 20 DEG C, pressure is 300MPa.
3. vacuum degassing sintering: the blank after isostatic pressed is placed in vacuum drying oven and carried out vacuum degassing sintering, and vacuum is maintained at 10-2-10-3Pa, sintering temperature is 400 DEG C, and sintering time is 6 hours.
4. hot rolling: the blank after sintering is carried out multi-pass rolling at 400 DEG C, drafts be every time 30%, until the sheet material that blank is rolled to predetermined thickness.
5. annealing: be annealed the sheet material of hot rolling processing.
Pattern and performance detection:
4. adopting Archimedes's drainage that composite is carried out density measurement, density is 91.0%;
8. the metallographic structure utilizing optical microscope centering daughter board is observed.
9. the neutron utilizing China Engineering Physics Research Institute accelerates to carry out neutron absorption rate test on irradiation test machine, and neutron absorption rate is 92.4%.
Embodiment eight
Prepared by middle daughter board:
1. mixed powder: by the B that Al alloy powder and average particle size are 45 μm that average particle size is 45 μm4C powder, according to the ratio of mass percent 55%:45%, by two kinds of powder body mix homogeneously in batch mixer.
2. binder: by the powder of mix homogeneously, loads in isostatic pressing machine, and press temperature 60 DEG C, pressure is 300MPa.
3. vacuum degassing sintering: the blank after isostatic pressed is placed in vacuum drying oven and carried out vacuum degassing sintering, and vacuum is maintained at 10-2-10-3Pa, sintering temperature is 400 DEG C, and sintering time is 6 hours.
4. hot rolling: the blank after sintering is carried out multi-pass rolling at 400 DEG C, drafts be every time 30%, until the sheet material that blank is rolled to predetermined thickness.
5. annealing: be annealed the sheet material of hot rolling processing.
Pattern and performance detection:
10. adopting Archimedes's drainage that composite is carried out density measurement, density is 90.9%;
11. the metallographic structure utilizing optical microscope centering daughter board is observed.
12. the neutron utilizing China Engineering Physics Research Institute accelerates to carry out neutron absorption rate test on irradiation test machine, neutron absorption rate is 91.4%.
Embodiment nine
Prepared by middle daughter board:
1. mixed powder: by the B that Al alloy powder and average particle size are 45 μm that average particle size is 45 μm4C powder, according to the ratio of mass percent 55%:45%, by two kinds of powder body mix homogeneously in batch mixer.
2. binder: by the powder of mix homogeneously, loads in isostatic pressing machine, and press temperature 10 DEG C, pressure is 300MPa.
3. vacuum degassing sintering: the blank after isostatic pressed is placed in vacuum drying oven and carried out vacuum degassing sintering, and vacuum is maintained at 10-2-10-3Pa, sintering temperature is 400 DEG C, and sintering time is 6 hours.
4. hot rolling: the blank after sintering is carried out multi-pass rolling at 400 DEG C, drafts be every time 30%, until the sheet material that blank is rolled to predetermined thickness.
5. annealing: be annealed the sheet material of hot rolling processing.
Pattern and performance detection:
13. adopt Archimedes's drainage that composite is carried out density measurement, density is 80.9%;
14. the metallographic structure utilizing optical microscope centering daughter board is observed.
15. the neutron utilizing China Engineering Physics Research Institute accelerates to carry out neutron absorption rate test on irradiation test machine, neutron absorption rate is 81.8%.
From embodiment 2,3,4 it can be seen that the pressing pressure of isostatic pressing machine is extremely important for density and the absorbance of neutron absorber material, when other preparation condition phases likewise it is preferred that 205MPa.
From embodiment 5,6,4,8,9 it can be seen that the press temperature of isostatic pressing machine is extremely important for density and the absorbance of neutron absorber material, press temperature within the scope of 20-80 DEG C very nearly the same, there is good density and absorbance.

Claims (5)

1. one kind has high B4The preparation method of C content neutron absorber plate, it is characterised in that: by Al alloy powder and B4After C powder mix homogeneously, vacuum-sintering, carry out hot rolling, after being rolling to predetermined scheme size, be annealed processing, make density and can reach the high B of 99.2%4The neutron absorber plate of C content.
2. one as claimed in claim 1 has high B4The preparation method of C content neutron absorber plate, it is characterised in that specifically comprise the following steps that
Mixed powder: by Al alloy powder and B4C powder, according to the ratio of mass percent 90-35%:10-65%, by two kinds of powder body mix homogeneously in batch mixer;
Binder: by the powder of mix homogeneously, loads in isostatic pressing machine, and press temperature is at 20-80 DEG C, and pressure is 100-400MPa;
Vacuum degassing sinters: the blank after isostatic pressed is placed in vacuum drying oven and carried out vacuum degassing sintering, and vacuum is maintained at 10-2-10-3Pa, sintering temperature is 300-440 DEG C, and sintering time is 5-15 hour;
Hot rolling: the blank after sintering is carried out multi-pass rolling at 300-440 DEG C, and drafts is every time 10-40%, until being rolled to the sheet material of predetermined thickness by blank;
Annealing: be annealed the sheet material of hot rolling processing, make neutron absorber material.
3. one as claimed in claim 2 has high B4The preparation method of C content neutron absorber plate, it is characterised in that: the average particle size of described Al alloy powder is 40-55 μm, described B4The average particle size of C powder is 20-50 μm.
4. one as claimed in claim 2 has high B4The preparation method of C content neutron absorber plate, it is characterised in that: the pressing pressure of described isostatic pressing machine is 205MPa.
5. one as claimed in claim 2 has high B4The preparation method of C content neutron absorber plate, it is characterised in that specifically comprise the following steps that
Mixed powder: by the B that Al alloy powder and average particle size are 20 μm that average particle size is 40 μm4C powder, according to the ratio of mass percent 68%:32%, by two kinds of powder body mix homogeneously in batch mixer;
Binder: by the powder of mix homogeneously, loads in isostatic pressing machine, press temperature 80 DEG C, and pressure is 205MPa;
Vacuum degassing sinters: the blank after isostatic pressed is placed in vacuum drying oven and carried out vacuum degassing sintering, and vacuum is maintained at 10-2-10-3Pa, sintering temperature is 350 DEG C, and sintering time is 10 hours;
Hot rolling: the blank after sintering is carried out multi-pass rolling at 350 DEG C, drafts be every time 25%, until the sheet material that blank is rolled to predetermined thickness;
Annealing: be annealed the sheet material of hot rolling processing.
CN201610141574.XA 2016-03-11 2016-03-11 Preparing method for neutron absorption plate with high B4C content Pending CN105671373A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201610141574.XA CN105671373A (en) 2016-03-11 2016-03-11 Preparing method for neutron absorption plate with high B4C content

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201610141574.XA CN105671373A (en) 2016-03-11 2016-03-11 Preparing method for neutron absorption plate with high B4C content

Publications (1)

Publication Number Publication Date
CN105671373A true CN105671373A (en) 2016-06-15

Family

ID=56307581

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201610141574.XA Pending CN105671373A (en) 2016-03-11 2016-03-11 Preparing method for neutron absorption plate with high B4C content

Country Status (1)

Country Link
CN (1) CN105671373A (en)

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107008894A (en) * 2017-03-28 2017-08-04 江苏海龙核科技股份有限公司 A kind of preparation method of high neutron absorption rate neutron absorption composite material
CN108118229A (en) * 2018-01-29 2018-06-05 镇江华核装备有限公司 A kind of high-performance B4C/Al neutron absorption composite materials
CN109825743A (en) * 2019-03-20 2019-05-31 中国工程物理研究院材料研究所 A kind of application method of structure-function integration neutron absorber material
CN110408818A (en) * 2019-07-15 2019-11-05 江苏大学 One seed nucleus irradiated fuel store B4Cp/ Al neutron absorber material and preparation method thereof
CN111118329A (en) * 2020-01-19 2020-05-08 江苏大学 Preparation method and device of high-toughness high-neutron absorption aluminum-based composite material
CN112692062A (en) * 2021-03-24 2021-04-23 西安稀有金属材料研究院有限公司 Rolling method of boron-tungsten-aluminum metal composite shielding material

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5960387A (en) * 1982-09-30 1984-04-06 株式会社東芝 Neutron absorbing rod and manufacture therefor
CN102560168A (en) * 2010-12-23 2012-07-11 中国核动力研究设计院 Preparation method of high-density neutron absorbing plate
CN103614584A (en) * 2013-11-07 2014-03-05 海龙核材科技(江苏)有限公司 Preparation method of aluminium matrix composite with high B4C content
CN104308161A (en) * 2014-10-16 2015-01-28 中国工程物理研究院材料研究所 Preparation method of low-cost boron carbide/aluminum composite board
CN105200274A (en) * 2015-10-26 2015-12-30 哈尔滨工业大学 Neutron absorbing material and preparation method thereof

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5960387A (en) * 1982-09-30 1984-04-06 株式会社東芝 Neutron absorbing rod and manufacture therefor
CN102560168A (en) * 2010-12-23 2012-07-11 中国核动力研究设计院 Preparation method of high-density neutron absorbing plate
CN103614584A (en) * 2013-11-07 2014-03-05 海龙核材科技(江苏)有限公司 Preparation method of aluminium matrix composite with high B4C content
CN104308161A (en) * 2014-10-16 2015-01-28 中国工程物理研究院材料研究所 Preparation method of low-cost boron carbide/aluminum composite board
CN105200274A (en) * 2015-10-26 2015-12-30 哈尔滨工业大学 Neutron absorbing material and preparation method thereof

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107008894A (en) * 2017-03-28 2017-08-04 江苏海龙核科技股份有限公司 A kind of preparation method of high neutron absorption rate neutron absorption composite material
CN107008894B (en) * 2017-03-28 2019-03-22 江苏海龙核科技股份有限公司 A kind of preparation method of high neutron absorption rate neutron absorption composite material
CN108118229A (en) * 2018-01-29 2018-06-05 镇江华核装备有限公司 A kind of high-performance B4C/Al neutron absorption composite materials
CN109825743A (en) * 2019-03-20 2019-05-31 中国工程物理研究院材料研究所 A kind of application method of structure-function integration neutron absorber material
CN110408818A (en) * 2019-07-15 2019-11-05 江苏大学 One seed nucleus irradiated fuel store B4Cp/ Al neutron absorber material and preparation method thereof
CN111118329A (en) * 2020-01-19 2020-05-08 江苏大学 Preparation method and device of high-toughness high-neutron absorption aluminum-based composite material
CN112692062A (en) * 2021-03-24 2021-04-23 西安稀有金属材料研究院有限公司 Rolling method of boron-tungsten-aluminum metal composite shielding material

Similar Documents

Publication Publication Date Title
CN105671373A (en) Preparing method for neutron absorption plate with high B4C content
CN105200274A (en) Neutron absorbing material and preparation method thereof
Troyanov et al. Prospects for using nitride fuel in fast reactors with a closed nuclear fuel cycle
CN104844190B (en) A kind of preparation method of fluor-apatite ceramic solidification body
CN106045495A (en) Method for preparing porous fluorapatite ceramic adsorbing radioactive nuclide
Drera et al. Thorium fuel production and results from beginning of life irradiation
CN112251666A (en) Austenitic stainless steel forging for spent fuel post-treatment and manufacturing method thereof
CN104952492B (en) Carry gadolinia fuel rod and with the fuel assembly and pressurized water reactor core for carrying gadolinia fuel rod
US3641227A (en) Manufacture of ceramic artefacts having pores
Kamath Recycle fuel fabrication for closed fuel cycle in India
Pecko et al. Comparative study of irradiated and hydrogen implantation damaged German RPV steels from PAS point of view
Wang et al. Preparation of UO2/TiO2 composite ceramic fuel by sol gel-press forming method
Troyanov et al. Program and results of reactor tests of mixed nitride fuel for fast reactors
CN109824355B (en) Treatment method of radioactive waste organic solvent tributyl phosphate pyrolysis furnace ash
Zhu et al. Uranium extraction from TRISO-coated fuel particles using supercritical CO2 containing tri-n-butyl phosphate
CN109378097B (en) Method for preparing simulated spent fuel
Nagarajan et al. Sol-gel processes for nuclear fuel fabrication
CN108538417A (en) A method of being directly separated uranium dioxide or spentnuclear fuel rare earth elements
Mukerjee et al. Fabrication technologies for ThO2-based fuel
Wang et al. Effects of TiO2 on the sintering densification of UO2–Gd2O3 burnable poison fuel
KR100969640B1 (en) A fabrication method of nuclear fuel pellet by using high burnup spent nuclear fuel containing metal impurities
CN106847353B (en) Lutetium oxide target piece pellet preparation process
KR20110034347A (en) A fabrication method of nuclear fuel pallet for heavy water reactor using spent nuclear fuel
Rogozkin et al. Results of U 0.55 Pu 0.45 N and U 0.4 Pu 0.6 N mixed mononitride fuel tests in a bor-60 reactor to burnup 12% ha
CN111263967A (en) Method for preparing a powder based on oxides of uranium, at least one minor actinide and optionally plutonium

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
WD01 Invention patent application deemed withdrawn after publication
WD01 Invention patent application deemed withdrawn after publication

Application publication date: 20160615