CN110277177B - Method for closing gap between fuel pellet and cladding in target - Google Patents

Method for closing gap between fuel pellet and cladding in target Download PDF

Info

Publication number
CN110277177B
CN110277177B CN201910495310.8A CN201910495310A CN110277177B CN 110277177 B CN110277177 B CN 110277177B CN 201910495310 A CN201910495310 A CN 201910495310A CN 110277177 B CN110277177 B CN 110277177B
Authority
CN
China
Prior art keywords
target
cladding
fuel
cladding tube
gap
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.)
Active
Application number
CN201910495310.8A
Other languages
Chinese (zh)
Other versions
CN110277177A (en
Inventor
尹邦跃
柯国土
吴学志
刘兴民
任劲如
屈哲昊
郑新海
魏国良
王轩
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.)
China Institute of Atomic of Energy
Original Assignee
China Institute of Atomic of Energy
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 China Institute of Atomic of Energy filed Critical China Institute of Atomic of Energy
Priority to CN201910495310.8A priority Critical patent/CN110277177B/en
Publication of CN110277177A publication Critical patent/CN110277177A/en
Application granted granted Critical
Publication of CN110277177B publication Critical patent/CN110277177B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/06Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • G21C17/07Leak testing
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/16Details of the construction within the casing
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Pressure Welding/Diffusion-Bonding (AREA)

Abstract

The invention belongs to the technical field of nuclear fuel preparation, and relates to a method for closing a gap between a fuel pellet and a cladding in a target. The method comprises the following steps: (1) loading the fuel pellet into a cladding tube, sealing the upper end and the lower end with the cladding tube by vacuum electron beam welding without filling high-purity helium gas to prepare a target; (2) and putting the target piece into a hot isostatic pressing furnace for hot isostatic pressing treatment, so that the clearance between the fuel pellets in the target piece and the cladding is closed. By using the method for closing the fuel pellet and the cladding gap in the target, the fuel pellet and the cladding gap in the target can be better closed without damaging the integrity of the cladding tube and the inner pellets.

Description

Method for closing gap between fuel pellet and cladding in target
Technical Field
The invention belongs to the technical field of nuclear fuel preparation, and relates to a method for closing a gap between a fuel pellet and a cladding in a target.
Background
The target is formed by loading fuel pellets into a cladding tube and welding and sealing the cladding tube with upper and lower end heads respectively. When fuel elements or targets are manufactured using conventional fuel pellet tubulation processes, there is always a certain gap between the pellets and the inner wall of the cladding. In order to improve the thermal conductivity, it is often necessary to fill the component or target with high purity helium gas under pressure. However, under the condition that the excircle of the sintered pellet is not ground, the outer diameter of the pellet is difficult to accurately control, the outer diameter of the pellet is widely distributed, and the manufacturing quality of elements or targets is greatly influenced. If the outer diameter of the core block is smaller, the clearance is too large, and the heat-conducting performance and the irradiation safety are influenced; on the contrary, if the external diameter of the pellet is bigger, the pellet is difficult to be put into the cladding tube and is temporarily scrapped; if the gap is not uniform, the heat conduction and temperature distribution will also be non-uniform.
To date, the most popular way to eliminate the clearance between the pellets and the inner cladding wall has been to use a co-thermal extrusion process to form a metallurgical bond between the pellets and the cladding, forming an integral plate-type fuel element or target, such as the plate-type U used in research stacks3Si2-Al dispersed fuel and Al-NpO2The neptunium target was dispersed (earlier by co-thermal extrusion).
However, when minor actinide materials such as Pu, Np, Am, Cm and the like with high toxicity and strong radioactivity are manufactured by adopting a co-hot extrusion process, equipment and materials are required to be placed in a sealed and shielded glove box, and the difficulty in operation and maintenance is very large; and the process is complex, the efficiency is low, and the rejection rate is high. If a neptunium target is made by a co-thermal extrusion process, the pellets and cladding are dissolved together by the solvent during post-treatment after irradiation, resulting in too much radioactive waste.
Therefore, in view of the principles of high irradiation safety, high irradiation conversion yield, less post-treatment waste, simple manufacturing equipment and process, low comprehensive cost and the like of the neptunium target, a new efficient and economical technology for closing the clearance between the pellet and the cladding needs to be developed.
Disclosure of Invention
It is an object of the present invention to provide a method of closing the fuel pellet to cladding gap in a target that better closes the fuel pellet to cladding gap in the target without compromising the integrity of the cladding and the inner pellets.
To achieve this object, in a basic embodiment, the present invention provides a method of closing a gap between a fuel pellet and a cladding within a target, the method comprising the steps of:
(1) loading the fuel pellet into a cladding tube, sealing the upper end and the lower end with the cladding tube by vacuum electron beam welding without filling high-purity helium gas to prepare a target;
(2) and putting the target piece into a hot isostatic pressing furnace for hot isostatic pressing treatment, so that the clearance between the fuel pellets in the target piece and the cladding is closed.
The principle of the invention is illustrated as follows.
Taking pellet tube-loading neptunium target as an example, Al-NpO meeting the design technical conditions is firstly adopted2The fuel pellets are loaded into a 6061 aluminum alloy cladding tube with a gap between the pellets and the inner wall of the cladding, and the gap is not uniform throughout. Then, the upper and lower end heads of the target are welded by vacuum electron beam instead of TIG welding without filling high-purity helium gasAnd respectively welding and sealing with the aluminum alloy cladding tubes, checking the welding line to be qualified by a helium leak detector, and determining the surface pollution degree of the target piece to be qualified after decontamination. And then, putting the target piece into a hot isostatic pressing furnace for heating and pressurizing, preserving heat and maintaining pressure for a certain time, and carrying out uniform extrusion plastic deformation on the cladding tube under the action of temperature and uniform isostatic pressure so as to close the gap between the pellet in the cladding and the inner wall of the cladding.
Hot Isostatic Pressing (HIP) is a common sintering process in the field of powder metallurgy (cf. textbook "principles of powder metallurgy" of the university of south china (edited by huangpeyun, published by the metallurgical industry, 1997, page 226)). The powder is put into a glass or iron sheath which is not melted at high temperature, is easy to deform and does not react with the powder, and the sheath is welded and sealed after being vacuumized; and then putting the mixture into a HIP furnace for heating, introducing high-purity argon for pressurizing, and enabling the pressure to uniformly act on the outer surface of the sheath so as to cause the powder in the sheath to uniformly shrink and densify. Or after pressureless sintering, the sintered body with the relative density of more than 94 percent and no open pore is directly placed into a HIP furnace without a sheath for high-temperature high-pressure treatment to shrink and close the closed pore, thereby further improving the densification and mechanical properties of the material. The highest temperature of the HIP furnace treatment is 2000 ℃ and the highest pressure is 200 MPa.
According to Al-20 wt% of NpO2The neptunium target piece is designed under the technical conditions that the clearance between the outer diameter of the pellet and the inner wall of the outer casing and the clearance between the inner diameter of the pellet and the outer wall of the inner casing are both 0.1mm, and the deviation between the inner diameter and the outer diameter of the pellet is required to be 0.05 mm. In fact, for the pellet whose excircle is not ground after sintering, it is difficult to accurately control the inner diameter and outer diameter, and the inner diameter and outer diameter are changed due to the fluctuation of the powder performance, the forming die, the sintering temperature, the vacuum degree, the sintering time and other factors. It is necessary to study the critical process parameters of optimization of hot isostatic pressing, temperature, pressure, time, etc., to ensure that the gap is just closed but no severe elemental diffusion reactions have taken place (e.g., changes in the gap are observed using radiographic techniques), so that the pellets and cladding tube can be separated more easily after irradiation, and to ensure that the target and pellets are intact, i.e., the target does not undergo significant distortion, nor the pellets do not deform or crack. Heat preservationAnd after the pressing is finished, cooling along with the furnace, taking out the target, and then carrying out subsequent target assembly.
In a preferred embodiment, the invention provides a method of closing the gap between fuel pellets and cladding within a target wherein in step (1) the weld is also tested for helium leak detection after vacuum electron beam welding and for contamination after decontamination of the target surface.
In a preferred embodiment, the invention provides a method for closing the gap between the fuel pellet and the cladding in the target, wherein in the step (1) and the step (2), the fuel pellet is Al-NpO2Fuel pellets or U3Si2-Al fuel pellets.
In a preferred embodiment, the present invention provides a method for closing the gap between the fuel pellets and the cladding in the target, wherein in step (1) and step (2), the cladding tube is an aluminum alloy cladding tube.
In a preferred embodiment, the present invention provides a method for closing the gap between fuel pellets and cladding in a target, wherein in step (1) and step (2), the cladding tube is a 6061 aluminum alloy cladding tube.
In a preferred embodiment, the invention provides a method for closing the gap between the fuel pellet and the cladding in the target, wherein in the step (2), the hot isostatic pressing treatment is carried out at the temperature of 400-500 ℃, the pressure of 50-200MPa and the time of 30-60 min.
The method has the advantages that the method for closing the gap between the fuel pellet and the cladding in the target can better close the gap between the fuel pellet and the cladding in the target without damaging the integrity of the cladding tube and the inner pellet.
The invention still assembles the component or the target by the traditional pellet tubulation process, and carries out Hot Isostatic Pressing (HIP) treatment on the vacuum welding sealed component or the target, so that the clearance between the pellet and the inner wall of the cladding is closed, and simultaneously, the integral appearance structure and the size of the component or the target are ensured to be unchanged, thereby being beneficial to fast heat conduction of the component or the target during irradiation in a reactor and improving the irradiation safety. Compared with the traditional co-heating extrusion process, the innovative process is simple and convenient, the product qualification rate is high, the radioactive material is completely sealed when the HIP treatment is carried out, and the production operation safety is higher. In addition, the invention can optimize the design parameters of elements or target pieces on the premise of ensuring the irradiation safety, thereby improving the irradiation yield and the economy.
Detailed Description
An exemplary method of closing the fuel pellet-to-cladding gap within a target of the present invention comprises the steps of:
(1) mixing fuel pellets (Al-NpO)2Fuel pellets or U3Si2Al fuel pellets) were packed in a cladding tube (6061 aluminum alloy cladding tube) without filling high purity helium gas, and the upper and lower end heads were sealed with the cladding tube by vacuum electron beam welding, respectively, to produce a target. And after the vacuum electron beam welding, performing helium leak detector detection on the welding seam, and performing pollution degree detection after the surface of the target piece is decontaminated.
(2) And putting the target piece into a hot isostatic pressing furnace for hot isostatic pressing treatment, so that the clearance between the fuel pellets in the target piece and the cladding is closed. The hot isostatic pressing treatment temperature is 400-500 ℃, the pressure is 50-200MPa, and the time is 30-60 min.
Table 1 shows Al-20 wt% NpO2The conditions of the hot isostatic pressing of the target and the experimental results (it can be seen that temperature is the most significant factor).
TABLE 1 Al-20 wt% NpO2Conditions and experimental results of hot isostatic pressing of target
Figure BDA0002087198660000041
Figure BDA0002087198660000051
It can be seen that:
(1) HIP treatment is carried out for 60min at the temperature of 400 ℃ and the pressure of 50-200MPa, and the gap is closed.
(2) When the temperature is 450 ℃ and the pressure is 50-200MPa, the gap can be closed by HIP treatment for 60min, and the integrity of the cladding tube and the inner core block is not damaged.
(3) When the temperature is 500 ℃ and the pressure is 50-200MPa, the HIP treatment is carried out for 40min, and the effect is good.
Therefore, the optimum HIP treatment process parameters are: the temperature is 400 ℃ and 500 ℃, the pressure is 50-200MPa, and the time is 30-60 min.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations. The foregoing examples or embodiments are merely illustrative of the present invention, which may be embodied in other specific forms or in other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.

Claims (6)

1. A method of closing a gap between a fuel pellet and a cladding within a target, the method comprising the steps of:
(1) loading the fuel pellet into a cladding tube, sealing the upper end and the lower end with the cladding tube by vacuum electron beam welding without filling high-purity helium gas to prepare a target;
(2) and putting the target piece into a hot isostatic pressing furnace for hot isostatic pressing treatment, so that the clearance between the fuel pellets in the target piece and the cladding is closed.
2. The method of claim 1, wherein: and (2) in the step (1), after the vacuum electron beam welding, performing helium leak detector detection on the welding seam, and performing pollution degree detection after the surface of the target piece is decontaminated.
3. The method of claim 1, wherein: in the step (1) and the step (2), the fuel pellet is Al-NpO2Fuel pellets or U3Si2-Al fuel pellets.
4. The method of claim 1, wherein: in the step (1) and the step (2), the cladding tube is an aluminum alloy cladding tube.
5. The method of claim 1, wherein: in the step (1) and the step (2), the cladding tube is a 6061 aluminum alloy cladding tube.
6. The method of claim 1, wherein: in the step (2), the hot isostatic pressing treatment temperature is 400-.
CN201910495310.8A 2019-06-06 2019-06-06 Method for closing gap between fuel pellet and cladding in target Active CN110277177B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201910495310.8A CN110277177B (en) 2019-06-06 2019-06-06 Method for closing gap between fuel pellet and cladding in target

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201910495310.8A CN110277177B (en) 2019-06-06 2019-06-06 Method for closing gap between fuel pellet and cladding in target

Publications (2)

Publication Number Publication Date
CN110277177A CN110277177A (en) 2019-09-24
CN110277177B true CN110277177B (en) 2020-11-24

Family

ID=67960630

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201910495310.8A Active CN110277177B (en) 2019-06-06 2019-06-06 Method for closing gap between fuel pellet and cladding in target

Country Status (1)

Country Link
CN (1) CN110277177B (en)

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2842402C2 (en) * 1978-09-29 1982-06-09 Nukem Gmbh, 6450 Hanau Process for the production of ceramic fuel pellets for nuclear reactors
US5383228A (en) * 1993-07-14 1995-01-17 General Electric Company Method for making fuel cladding having zirconium barrier layers and inner liners
CN103295652B (en) * 2012-02-24 2017-02-08 上海核工程研究设计院 Nuclear fuel rod with ceramic cladding and metallic pellet
CN103345951B (en) * 2013-06-21 2016-05-04 中国原子能科学研究院 (U,Np)O2The preparation technology of transmuting fuel pellet and target part
CN103691956B (en) * 2014-01-03 2016-06-22 中国原子能科学研究院 Annular thin wall Al-NpO2The preparation technology of disperse pellet
JP2021501335A (en) * 2017-10-31 2021-01-14 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー High temperature atomic fuel system for thermal neutron reactors

Also Published As

Publication number Publication date
CN110277177A (en) 2019-09-24

Similar Documents

Publication Publication Date Title
CN105803267B (en) Shield neutron and gamma-ray used by nuclear reactor aluminum matrix composite and preparation method
CA1190332A (en) Method of preparing spent nuclear fuel rods for long- term storage
CN100586638C (en) Manufacture technique for thermonuclear reactor envelope containing flow-passage parts
CN106702192A (en) Boron carbide aluminum matrix composite material and preparation method thereof
CN111185686A (en) Method for in-situ connection of SiC/SiC core cladding tube by adopting Zr alloy end plug
CN103345951A (en) (U, np) O2transmutation fuel pellet and target preparation process
CN104607878B (en) The preparation method of W/Cu/CuCrZr composite components
US3276867A (en) Cermet materials and process of making
CN109321809B (en) Radiation-absorbing nano-powder stainless steel and manufacturing method and application thereof
CN110277177B (en) Method for closing gap between fuel pellet and cladding in target
CN105057671B (en) A kind of method that utilization hot isostatic press welding technique prepares neutron absorber plate
KR20180056387A (en) Method for repairing defects on hot parts of turbomachines through hybrid hot isostatic pressing (hip) process
US20210375494A1 (en) Method to pressurize sic fuel cladding tube before end plug sealing by pressurization pushing spring loaded end plug
CN106735190A (en) A kind of preparation method of particle enhanced aluminum-based composite material large scale thick-wall tube
US20040141866A1 (en) Manufacture of annular cermet articles
CN206772020U (en) The pressure sintering apparatus of high-density niobium oxide Nb2O5 rotary target materials
WO2020150976A1 (en) Coated fuel particle, inert matrix dispersed fuel pellet and integrated fuel rod, and fabrication methods therefor
RU2305334C1 (en) Method for manufacturing ceramic fuel-core rod for nuclear reactor fuel element
CN106381439B (en) A kind of method that nano oxide dispersion reinforcing martensite heat-resistant steel is prepared using explosive sintering
CN113953628B (en) Helium-filled hole-blocking welding method for aluminum alloy cladding target piece
CN115521150A (en) Boron carbide/lead composite radiation-proof material, preparation method and application thereof
CN110153420B (en) Titanium alloy protection cabin device and laser additive manufacturing method
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
CN115894033B (en) Preparation method of large-size magnesium fluoride moderated body
CN206471152U (en) A kind of electrical penetration feedthrough for nuclear power station

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant