CN102618753B - Zr-Sn-Fe-Cr intermediate alloy of zirconium alloy for nuclear reactor and preparation process - Google Patents

Zr-Sn-Fe-Cr intermediate alloy of zirconium alloy for nuclear reactor and preparation process Download PDF

Info

Publication number
CN102618753B
CN102618753B CN 201210044148 CN201210044148A CN102618753B CN 102618753 B CN102618753 B CN 102618753B CN 201210044148 CN201210044148 CN 201210044148 CN 201210044148 A CN201210044148 A CN 201210044148A CN 102618753 B CN102618753 B CN 102618753B
Authority
CN
China
Prior art keywords
alloy
melting
nuclear reactor
tin
zirconium
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.)
Expired - Fee Related
Application number
CN 201210044148
Other languages
Chinese (zh)
Other versions
CN102618753A (en
Inventor
郑杰
张金波
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.)
JIACHENG RARE METAL MATERIALS CO Ltd BAOJI CITY
Original Assignee
JIACHENG RARE METAL MATERIALS CO Ltd BAOJI CITY
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 JIACHENG RARE METAL MATERIALS CO Ltd BAOJI CITY filed Critical JIACHENG RARE METAL MATERIALS CO Ltd BAOJI CITY
Priority to CN 201210044148 priority Critical patent/CN102618753B/en
Publication of CN102618753A publication Critical patent/CN102618753A/en
Application granted granted Critical
Publication of CN102618753B publication Critical patent/CN102618753B/en
Expired - Fee Related legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Abstract

The invention provides a Zr-Sn-Fe-Cr intermediate alloy of a zirconium alloy for nuclear reactor and preparation process, which is added in the zirconium alloy smelting to ensure the content of each element to be stable and accurate. The preparation process of the alloy comprises dosing according to the ratio-vacuum plasma argon arc primary smelting-suspended furnace smelting-ingot casting and turning-analysis-entering warehouses. Due to the fact that the intermediate alloy is added into the smelting of the zirconium alloy, each element component is ensured to be accurate and stable. Simultaneously, vacuum plasma argon arc primary smelting is adopted, because a tin element has a low melting point, the process enables the metals to be primarily alloyed, and the volatilization of the tin element is avoided.

Description

The used by nuclear reactor zirconium alloy is smelted with Zr-Sn-Fe-Cr master alloy and preparation technology
Technical field
The invention belongs to the manufacturing of master alloy in the alloy manufacturing technology field, particularly used by nuclear reactor zirconium alloy smelting process.
Background technology
The heat exchanger zirconium alloy pipe is made special-purpose zirconium alloy in the nuclear reactor, contain multiple elements such as Zr, Sn, Fe, in zirconium alloy is smelted, generally all be directly to add various element simple substances, but because element S n fusing point is very low, directly interpolation often causes inclined to one side tin, makes the tin element addition be difficult to control, cause the alloy smelting qualification rate can be very low, generally have only about 30%.
Summary of the invention
The object of the invention provides a kind of used by nuclear reactor zirconium alloy and smelts with Zr-Sn-Fe-Cr master alloy, and this alloy adds in zirconium alloy is smelted can guarantee that each constituent content is accurately stable.
For achieving the above object, used by nuclear reactor zirconium alloy of the present invention is smelted with Zr-Sn-Fe-Cr master alloy, and its each component weight percent content is as follows:
The preparation technology of described alloy is: according to the first melting of proportion ingredient → vacuum plasma argon arc → shower furnace melting → ladle barrow bits → analysis → warehouse-in.
Zr atomic level zirconium sponge during proportioning; Sn " 0 " level tin, and roll into the tin band; Fe adopts straight iron powder, Fe 〉=99.9%; The pure chromium powder that Cr adopts; And with the tin band various raw material packet are made the alloy bead that weight is no less than 50g.The melting of shower furnace argon filling prevents the tin loss; Adopt the water-cooled red copper crucible to prevent the pollution of other element impurity simultaneously in the shower furnace.
The present invention is owing to adopt the mode of master alloy to join in the smelting of zirconium alloy, guaranteed each elemental composition accurately and stable, adopted the first melting of vacuum plasma argon arc simultaneously, because of the tin element fusing point low, adopt this technology to make the preliminary alloying of alloy, prevent the volatilization of tin element.In addition
Argon filling melting during the shower furnace melting prevents the tin loss; Adopt the water-cooled red copper crucible in the shower furnace, prevented the dirty element of other element impurity.
Embodiment
1, master alloy nominal composition: Zr-33Sn-4.6Fe-2.3Cr
2, chemical ingredients sees the following form:
Figure GDA0000287350072
3, the technological process of production:
3.1 proportioning: the Zr-35Sn-4.55Fe-2.55Cr proportioning 100g that weighs
Zr adopts the atomic level zirconium sponge, and Sn adopts " 0 " level tin shavings and the thick Sn band of 0.5mm, and Fe adopts pure Fe powder, and Fe 〉=99.9% Cr adopts pure Cr powder Cr 〉=99.6%
Prepare burden by the 100g that weighs, wherein zirconium sponge: 57.9g, the Sn bits add Sn band: 35g, the Fe powder: the bead that packs into heavy 100g after 4.55g Cr powder: 2.55g weighs with the Sn band.
3.2 the first melting of vacuum plasma argon arc
50 of the vacuum chambers of at every turn packing into have been with the alloy beads that packed with Sn, be evacuated to below the 1Pa, adopt the vacuum plasma argon welder to alloy ball melting one by one, melting is to completely liq, solidify the back shelling and continue melting, melting electric current 250 ~ 300A voltage 30 ~ 40V.
3.3 shower furnace melting
Shove charge: 50 of each shove charges are the alloy ball of melting tentatively, about 5kg;
Smelting furnace vacuum :≤1Pa/min;
Argon filling pressure :-0.2 normal atmosphere;
Power: 10KW/3 min-20KW/5 min-30KW/5min-40KW/5 min-50KW/5 min-60KW/ fusing-40KW/ extremely fully is incubated 10 min-liquid;
Cooling time: 2h.

Claims (5)

1. the used by nuclear reactor zirconium alloy is smelted and is used the Zr-Sn-Fe-Cr master alloy, it is characterized in that each component weight percent content is as follows: Sn 30-36, Fe 4.0-5.0, Cr 2.0-2.6, C≤0.08, N≤0.01, O≤0.10, H≤0.003, Zr surplus, each component adds up to 100%.
2. used by nuclear reactor zirconium alloy as claimed in claim 1 is smelted and is used the Zr-Sn-Fe-Cr master alloy, and its preparation technology is: according to the first melting of proportion ingredient → vacuum plasma argon arc → shower furnace melting → ladle barrow bits → analysis → warehouse-in.
3. used by nuclear reactor zirconium alloy as claimed in claim 2 is smelted the preparation technology with the Zr-Sn-Fe-Cr master alloy, it is characterized in that: Zr atomic level zirconium sponge during proportioning; Sn " 0 " level tin, and roll into the tin band; Fe adopts straight iron powder, Fe 〉=99.9%; The pure chromium powder that Cr adopts; And with the tin band all the other raw material packet are made the alloy bead that weight is no less than 50g.
4. smelt the preparation technology who uses the Zr-Sn-Fe-Cr master alloy as claim 2 or 3 described used by nuclear reactor zirconium alloys, it is characterized in that the melting of shower furnace argon filling, prevent the tin loss; Adopt the water-cooled red copper crucible to prevent the pollution of other element impurity simultaneously in the shower furnace.
5. used by nuclear reactor zirconium alloy according to claim 2 is smelted the preparation technology with the Zr-Sn-Fe-Cr master alloy, the technology that it is characterized in that the first melting of vacuum plasma argon arc is: 50 the alloy beads that packed with the Sn band of vacuum chamber of at every turn packing into, be evacuated to below the 1Pa, adopt the vacuum plasma argon welder to alloy ball melting one by one, melting is to completely liq, solidify the back shelling and continue melting, melting electric current 250 ~ 300A; Voltage 30 ~ 40V; Simultaneously the shower furnace melting technology is: shove charge: 50 of each shove charges are the alloy ball of melting tentatively, weight 5kg; Smelting furnace vacuum :≤1Pa/min; Argon filling pressure :-0.2 normal atmosphere; Power: 10kW/3 min-20kW/5 min-30kW/5min-40kW/5 min-50kW/5 min-60kW/ is fusing-40kW extremely fully; Be incubated 10 min-liquid; Cooling time: 2h.
CN 201210044148 2012-02-24 2012-02-24 Zr-Sn-Fe-Cr intermediate alloy of zirconium alloy for nuclear reactor and preparation process Expired - Fee Related CN102618753B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN 201210044148 CN102618753B (en) 2012-02-24 2012-02-24 Zr-Sn-Fe-Cr intermediate alloy of zirconium alloy for nuclear reactor and preparation process

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN 201210044148 CN102618753B (en) 2012-02-24 2012-02-24 Zr-Sn-Fe-Cr intermediate alloy of zirconium alloy for nuclear reactor and preparation process

Publications (2)

Publication Number Publication Date
CN102618753A CN102618753A (en) 2012-08-01
CN102618753B true CN102618753B (en) 2013-08-21

Family

ID=46558952

Family Applications (1)

Application Number Title Priority Date Filing Date
CN 201210044148 Expired - Fee Related CN102618753B (en) 2012-02-24 2012-02-24 Zr-Sn-Fe-Cr intermediate alloy of zirconium alloy for nuclear reactor and preparation process

Country Status (1)

Country Link
CN (1) CN102618753B (en)

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4164420A (en) * 1977-01-07 1979-08-14 Ugine Aciers Master alloy for the preparation of zirconium alloys

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS60190540A (en) * 1984-03-12 1985-09-28 Nippon Mining Co Ltd Production of zirconium alloy ingot for nuclear reactor

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4164420A (en) * 1977-01-07 1979-08-14 Ugine Aciers Master alloy for the preparation of zirconium alloys

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
JP昭60-190540A 1985.09.28

Also Published As

Publication number Publication date
CN102618753A (en) 2012-08-01

Similar Documents

Publication Publication Date Title
CN111378848B (en) Pre-melted slag for electroslag remelting for improving purity of GH4169 alloy return and preparation method thereof
EP3327154A1 (en) Method for preparing titanium or titanium aluminum alloy and byproduct- titanium-free cryolite through two-stage aluminothermic reduction
CN102994841A (en) Magnesium-based wear resisting and shock absorbing alloy and production method
CN103146943A (en) Red impure copper refining agent and preparation method thereof
CN102719682A (en) Smelting method of GH901 alloy
CN112011700B (en) Method for adding zirconium alloy ingot casting alloy elements
CN104294126A (en) Wear-resistant damping alloy
CN105002397B (en) K418 cast superalloy sublimate smelting processes
CN105618723A (en) Inert atmosphere-based skull melting and casting process adopting consumable titanium alloy electrode
CN102618753B (en) Zr-Sn-Fe-Cr intermediate alloy of zirconium alloy for nuclear reactor and preparation process
CN103741004B (en) CoS 2high capacity hydrogen storage alloy of catalysis and preparation method thereof
CN105950912B (en) A kind of preparation method of medical Zr 2.5Nb alloy cast ingots
CN109136642A (en) A kind of Ti-Mo intermediate alloy and its preparation method and application
CN102534272A (en) Processing method for high vacuum smelting of cobalt base molybdenum magnesium alloy
CN104625462B (en) A kind of mixed gas protected high tenacity carbon steel flux-cored wire
CN105132774A (en) Wear-resisting vibration-absorptive alloy material and production method thereof
CN105385915A (en) Wear-resisting magnesium alloy and production method
CN101857935B (en) Method for preparing magnesium base alloy material
CN104294130A (en) Self-lubricating damping alloy and preparation method thereof
CN102286673A (en) Preparation method of CuCr25Me alloy cast blank
CN106636668A (en) Waste electromagnetic wire copper refining agent and preparation method and application thereof
CN202162507U (en) Blank structure of tin-selenium intermediate alloy
CN105385914A (en) Magnesium-based wear-resisting and shock absorbing alloy
CN102766784A (en) Zinc alloy
CN105132773A (en) Wear-resisting damping alloy and production method

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
C14 Grant of patent or utility model
GR01 Patent grant
CF01 Termination of patent right due to non-payment of annual fee

Granted publication date: 20130821

Termination date: 20150224

EXPY Termination of patent right or utility model