CN112863721A - Uranium-based neutron gamma composite shielding material - Google Patents

Uranium-based neutron gamma composite shielding material Download PDF

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Publication number
CN112863721A
CN112863721A CN202011625306.8A CN202011625306A CN112863721A CN 112863721 A CN112863721 A CN 112863721A CN 202011625306 A CN202011625306 A CN 202011625306A CN 112863721 A CN112863721 A CN 112863721A
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CN
China
Prior art keywords
uranium
metal
gadolinium
melting
shielding material
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.)
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Application number
CN202011625306.8A
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Chinese (zh)
Inventor
康泰峰
聂皓
刘建成
王虹
单宏祎
牟雪婷
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China North Nuclear Fuel Co Ltd
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China North Nuclear Fuel Co Ltd
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Publication date
Application filed by China North Nuclear Fuel Co Ltd filed Critical China North Nuclear Fuel Co Ltd
Priority to CN202011625306.8A priority Critical patent/CN112863721A/en
Publication of CN112863721A publication Critical patent/CN112863721A/en
Pending legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F1/00—Shielding characterised by the composition of the materials
    • G21F1/02—Selection of uniform shielding materials
    • G21F1/08—Metals; Alloys; Cermets, i.e. sintered mixtures of ceramics and metals
    • G21F1/085—Heavy metals or alloys
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C1/00—Making non-ferrous alloys
    • C22C1/02—Making non-ferrous alloys by melting
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C43/00—Alloys containing radioactive materials

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  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Metallurgy (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Organic Chemistry (AREA)
  • Ceramic Engineering (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Measurement Of Radiation (AREA)
  • Compositions Of Macromolecular Compounds (AREA)

Abstract

The invention belongs to the technical field of nuclear material research and manufacturing, and particularly relates to a uranium-based neutron-gamma composite shielding material. A uranium-based neutron gamma composite shielding material is characterized in that metal gadolinium is added into a metal uranium matrix, and the addition range of the metal gadolinium is 0.1-2 wt%. The material is prepared by a vacuum melting method. The material is a dispersion type composite material formed by uniformly dispersing metal gadolinium in a uranium matrix. The uranium metal being a uranium-depleted metal, U thereof235The atomic number percentage of the isotope is less than 0.3 percent. The vacuum melting method comprises arc melting, induction melting and electron beam melting. Smelting 10kg of depleted uranium metal and 500g of gadolinium metal in a vacuum induction furnace, stirring after complete melting, then casting in a mold, cooling, and discharging after complete cooling; after the ingot is taken out of the furnace and is dissected, the material structure is observed by using an optical microscope, and the metal gadolinium is in a second phaseThe mode is evenly dispersed in the depleted uranium matrix. The invention provides a material which can shield gamma rays and enhance the neutron moderation effect.

Description

Uranium-based neutron gamma composite shielding material
Technical Field
The invention belongs to the technical field of nuclear material research and manufacturing, and particularly relates to a uranium-based neutron-gamma composite shielding material.
Background
The shielding layer has important significance for the safe radiation and the effective utilization of radioactive sources.
For shielding neutron rays, the shielding material is generally made of a hydrogen element material. So that the neutrons can be quickly decelerated, the aim of moderating the neutrons when the neutrons penetrate through the shielding layer is fulfilled, and generally, materials which can achieve a good neutron moderating effect comprise water, paraffin and other substances. The metal gadolinium is a rare earth metal, is commonly used as a material for absorbing neutrons in an atomic reactor, is used as a control rod and a neutron absorber of a light water reactor and a fast neutron breeder reactor by utilizing the characteristic of large isotope neutron absorption cross section, and does not find an application example of singly adopting the metal gadolinium as a neutron source shielding material at present.
For shielding gamma rays, a generally mature technology is to use heavy metal materials to prepare, for example, lead, tungsten, depleted uranium and other heavy metal materials, wherein the depleted uranium material has a good application effect in gamma knife medical equipment and industrial flaw detectors due to its excellent ray shielding capability and good mechanical properties.
Disclosure of Invention
The invention aims to provide a uranium-based neutron-gamma composite shielding material, which is a material for shielding gamma rays and enhancing the neutron moderating effect by combining the ray shielding characteristics of depleted uranium and metal gadolinium.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
a uranium-based neutron gamma composite shielding material is characterized in that metal gadolinium is added into a metal uranium matrix, and the addition range of the metal gadolinium is 0.1-2 wt%.
The material is prepared by a vacuum melting method.
The material is a dispersion type composite material formed by uniformly dispersing metal gadolinium in a uranium matrix.
The uranium metal being a uranium-depleted metal, U thereof235The atomic number percentage of the isotope is less than 0.3 percent.
The vacuum melting method comprises arc melting, induction melting and electron beam melting.
Smelting 10kg of depleted uranium metal and 500g of gadolinium metal in a vacuum induction furnace, stirring after complete melting, then casting in a mold, cooling, and discharging after complete cooling; and after the ingot is taken out of the furnace and is dissected, observing the material structure by using an optical microscope, and uniformly dispersing the metal gadolinium in the depleted uranium matrix in a second phase mode.
The beneficial effects obtained by the invention are as follows:
a uranium-based neutron-gamma composite shielding material is formed by combining the ray shielding characteristics of depleted uranium and metal gadolinium, and the material can shield gamma rays and enhance the neutron moderating effect.
Detailed Description
The present invention will be described in detail with reference to specific examples.
The material is prepared by adding a certain proportion of metal gadolinium into a metal uranium matrix, wherein the addition range of the metal gadolinium is (0.1-2) wt% according to different neutron shielding effects.
The material is prepared by a vacuum melting method.
The material is a dispersion type composite material formed by uniformly dispersing metal gadolinium in a uranium matrix.
The material can be used for preparing required shielding material parts and parts by metal cold processing, hot processing and other methods.
The metal uranium is depleted uranium metal, U thereof235The atomic number percentage of the isotope is less than 0.3 percent.
The vacuum melting method is a general metal melting method, and includes, but is not limited to, arc melting, induction melting, electron beam melting, and the like.
Smelting 10kg of depleted uranium metal and 500g of gadolinium metal in a vacuum induction furnace, stirring by using a stirring device of smelting equipment after complete melting, then casting in a mold, cooling, and discharging after complete cooling.
And after the ingot is taken out of the furnace and is dissected, observing the material structure by using an optical microscope, and uniformly dispersing the metal gadolinium in the depleted uranium matrix in a second phase mode.
While the embodiments of the present invention have been described in detail, the embodiments are merely exemplary embodiments of the present invention, but the present invention is not limited to the embodiments, and various changes can be made without departing from the spirit of the present invention within the knowledge of those skilled in the art.

Claims (6)

1. A uranium-based neutron-gamma composite shielding material is characterized in that: metal gadolinium is added into the metal uranium matrix, and the addition range of the metal gadolinium is 0.1-2 wt%.
2. The uranium-based neutron-gamma composite shielding material of claim 1, wherein: the material is prepared by a vacuum melting method.
3. The uranium-based neutron-gamma composite shielding material of claim 1, wherein: the material is a dispersion type composite material formed by uniformly dispersing metal gadolinium in a uranium matrix.
4. The uranium-based neutron-gamma composite shielding material of claim 1, wherein: the uranium metal being a uranium-depleted metal, U thereof235The atomic number percentage of the isotope is less than 0.3 percent.
5. The uranium-based neutron-gamma composite shielding material of claim 2, wherein: the vacuum melting method comprises arc melting, induction melting and electron beam melting.
6. The uranium-based neutron-gamma composite shielding material of claim 4, wherein: smelting 10kg of depleted uranium metal and 500g of gadolinium metal in a vacuum induction furnace, stirring after complete melting, then casting in a mold, cooling, and discharging after complete cooling; and after the ingot is taken out of the furnace and is dissected, observing the material structure by using an optical microscope, and uniformly dispersing the metal gadolinium in the depleted uranium matrix in a second phase mode.
CN202011625306.8A 2020-12-31 2020-12-31 Uranium-based neutron gamma composite shielding material Pending CN112863721A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202011625306.8A CN112863721A (en) 2020-12-31 2020-12-31 Uranium-based neutron gamma composite shielding material

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202011625306.8A CN112863721A (en) 2020-12-31 2020-12-31 Uranium-based neutron gamma composite shielding material

Publications (1)

Publication Number Publication Date
CN112863721A true CN112863721A (en) 2021-05-28

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115874072A (en) * 2021-09-29 2023-03-31 中核北方核燃料元件有限公司 Preparation method of ray shielding material of electron irradiation accelerator

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1991009982A1 (en) * 1990-01-03 1991-07-11 Teleki Peter Method of influencing the strength of a metallic product
US5334847A (en) * 1993-02-08 1994-08-02 The United States Of America As Represented By The Department Of Energy Composition for radiation shielding
DE102005029511A1 (en) * 2005-06-24 2006-12-28 Siemens Ag Device used in medical X-ray devices comprises screen consisting of at least two materials for absorbing X-ray radiation
CN101528957A (en) * 2006-10-16 2009-09-09 法国原子能委员会 Erbium-containing zirconium alloy, method for preparing and shaping the same, and structural part containing said alloy
CN107342113A (en) * 2017-07-21 2017-11-10 中国核动力研究设计院 A kind of resistance to irradiation inorganic mask material of high temperature resistant
CN108195880A (en) * 2017-12-28 2018-06-22 中核北方核燃料元件有限公司 The detection method of nitrogen content in U-Gd-Zr pellets
CN108267498A (en) * 2017-12-28 2018-07-10 中核北方核燃料元件有限公司 The assay method of boron aluminium impurity content in a kind of uranium gadolinium zircaloy
CN110643859A (en) * 2019-08-30 2020-01-03 厦门大学 Aluminum-based composite material containing gadolinium-tungsten element and application thereof

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1991009982A1 (en) * 1990-01-03 1991-07-11 Teleki Peter Method of influencing the strength of a metallic product
US5334847A (en) * 1993-02-08 1994-08-02 The United States Of America As Represented By The Department Of Energy Composition for radiation shielding
DE102005029511A1 (en) * 2005-06-24 2006-12-28 Siemens Ag Device used in medical X-ray devices comprises screen consisting of at least two materials for absorbing X-ray radiation
CN101528957A (en) * 2006-10-16 2009-09-09 法国原子能委员会 Erbium-containing zirconium alloy, method for preparing and shaping the same, and structural part containing said alloy
CN107342113A (en) * 2017-07-21 2017-11-10 中国核动力研究设计院 A kind of resistance to irradiation inorganic mask material of high temperature resistant
CN108195880A (en) * 2017-12-28 2018-06-22 中核北方核燃料元件有限公司 The detection method of nitrogen content in U-Gd-Zr pellets
CN108267498A (en) * 2017-12-28 2018-07-10 中核北方核燃料元件有限公司 The assay method of boron aluminium impurity content in a kind of uranium gadolinium zircaloy
CN110643859A (en) * 2019-08-30 2020-01-03 厦门大学 Aluminum-based composite material containing gadolinium-tungsten element and application thereof

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115874072A (en) * 2021-09-29 2023-03-31 中核北方核燃料元件有限公司 Preparation method of ray shielding material of electron irradiation accelerator

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