CN102285769A - Special high-performance cement for nuclear island and preparation method thereof - Google Patents
Special high-performance cement for nuclear island and preparation method thereof Download PDFInfo
- Publication number
- CN102285769A CN102285769A CN 201110151123 CN201110151123A CN102285769A CN 102285769 A CN102285769 A CN 102285769A CN 201110151123 CN201110151123 CN 201110151123 CN 201110151123 A CN201110151123 A CN 201110151123A CN 102285769 A CN102285769 A CN 102285769A
- Authority
- CN
- China
- Prior art keywords
- cement
- grinding
- nuclear power
- nuclear
- power station
- 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
Links
Images
Landscapes
- Silicates, Zeolites, And Molecular Sieves (AREA)
Abstract
The invention discloses special high-performance cement for a nuclear island and a preparation method thereof. The special high-performance cement for the nuclear island comprises the following ingredients: 90.5 to 92.0 percent of cement clinker, 4.0 to 4.5 percent of limestone mixture and 4.0 to 5.0 percent of desulfurization gypsum, wherein the cement clinker comprises 0.910+/-0.01 percent of KH, 2.0+/-0.1 percent of SM and 1.0+/-0.1 percent of IM. The preparation method comprises: preparing a raw material by powder grinding, controlling process parameters, calcining the raw material in a rotary kiln, and preparing the cement clinker; grinding powder by using a cement powder grinding system and obtaining ground cement; and cooling. The prepared special high-performance cement for the nuclear island has the advantages of low water consumption, low hydratation heat (anti-cracking), high durability and the like.
Description
Technical field
The invention belongs to building material field, be specifically related to a kind of nuclear island of nuclear power station dedicated high performance cement and preparation method thereof.
Background technology
Cement is one of building industry three big basic materials, uses extensively, and consumption is big, have the title of " grain of building industry ".Since the practical application of Cement industry product, since a century and a half so far, produced lasting expansion, technology and equipment are updated, and kind and quality have also had great development.In recent years, China's new type nonaqueous cement obtains high speed development, the cement output height, and also kind, quality all reach or approach advanced international standards.
Utilize the superiority of nuclear energy power generation more and more to be subject to people's attention, China starts late in this respect, develop rapidly but had in recent years, as Daya Bay nuclear power plant's engineering is the famous nuclear power engineering of China, first phase engineering is completed and is put into operation, and the mountain range Australia nuclear power second phase also is constructed and put into operation in September, 2010.At present as in the Taishan Nuclear power plants of the advanced nuclear power technology project of China's third generation and the Yangjiang Nuclear power plants engineering also in full preparation construction.The position, nuclear reactor place of Nuclear power plants is called nuclear island, and position, turbo-generator place is called conventional island, is nuclear power plant concrete cast main construction.The cement quantity that is used for concrete main body engineering cast is big, high, the quality control of technical requirements sternly be well-known.Nuclear island of nuclear power station and conventional island concrete works with the characteristics of cement are: require early strength stable, and the later strength height, standard deviation is little, and hydration heat is low, and contract with dry rate is low, and is good with the admixture consistency, and foreign matter content and objectionable constituent content are few.And the nuclear island concrete mix generally must not change once determining, so that the quality in kind of cement must keep is stable, fluctuation is little.The hydration heat of cement is related to unlikely generation volume change and generation thermal cracking in the mass concrete casting process, and this prevents that for nuclear island of nuclear power station and conventional island nuclear leakage and nuclear pollution from being vital.In addition, the density of cement also has certain requirement, to guarantee density, security and the capability of resistance to radiation of nuclear island and conventional island deposit concrete.
The cement output of China accounts for about 50% of global output, is world's manufacture of cement first big country.In industrial production, new type dry kiln technology is because heat and mass is fast, and heat force intensity is concentrated, the grog good cooling results, so clinker quality is stable.Stable by the cement quality that dry method kiln grog is produced, excellent performance all is widely used at aspects such as industrial and covil construction, feedwater and drainage system, water conservancy and underground works, national defense construction.At present, conventional dry method kiln grog prescription: KH=0.920 ± 0.01, SM=2.7 ± 0.1, though the cement that this prescription is produced has obtained widespread use, also there are some shortcomings in IM=1.6 ± 0.1, can't satisfy the particular requirement of the construction of nuclear power station.
At present, common not enough as follows of cement:
1, grog mesosilicic acid DFP (C
3A) content height
C
3The A aquation is rapid, and heat release is many, and it is very fast to condense, and it is also very fast to harden, C
3A's is dry-shrinkage deformed big, and the sulfate resistance performance is poor.Therefore, C
3The cement that the higher grog of A content is produced is not suitable for the large volume engineering.And the grog C that conventional dry-process rotory kiln is produced
3A content is higher, and generally more than 8%, nuclear power cement requires≤6%, and therefore general cement can't satisfy the demand that nuclear power is built.
2, hydration heat of cement height
Cement with an amount of water mix after, can setting and harden become Shi Zhuanti with intensity, also be accompanied by phenomenons such as hydration heat and volume change simultaneously.The mineral composition of silicate cement mainly contains: C
3S, C
2S, C
3A and C
4AF, test shows: tricalcium aluminate (C in the cement
3A) and tricalcium silicate (C
3S) content is high more, and then hydration heat is also high more.
Nuclear power cement requires 3 days hydration heat≤251kJ/kg, 7 days hydration heat≤293kJ/kg, and the cement of present large-scale new type dry kiln is because of C
3A content height, hydration heat is also higher, the data that provide according to cement quality supervision and inspection station, Guangdong Province, general 3 days hydration heat of PII cement are 360-370kJ/kg, 7 days hydration heat are 420-430kJ/kg, and are high even reach more than the 450kJ/kg.This shows that general hydration heat of cement is higher than the requirement of nuclear power cement far away.
3, hydrated cementitious speed is fast, easily causes distress in concrete
C in four mineral compositions of grog
3The A aquation is the fastest, and general cement is because C
3A content is higher, so aquation is very fast.Hydrated cementitious is too fast, and temperature strain produces stress, causes concrete early stage cracking, and particularly the mass concrete cracking phenomena is more obvious.A large amount of engineering practice at present shows that a lot of little concrete structures of size also can be owing to internal temperature rise ftractures.
The cracking problem is the technical problem that has certain ubiquity in engineering construction, and in a single day the crack forms, and particularly basic through crack appears at important structure position, very harmful, it can reduce durability of structures, weakens bearing of component, may jeopardize the safe handling of buildings simultaneously.General hydrated cementitious speed is fast, and the concrete of preparation adds behind the water that thermal insulation warming can be easy to generate temperature difference crack up to more than 40 ℃ in 48 hours.Nuclear power plants can not go out least bit mistake when operation, more can not cause nuclear leakage because of concrete cracking, otherwise consequence is hardly imaginable, and the nuclear leakage accident of the Chernobyl Plant of Ukraine is exactly the warning taken from the overturned card ahead that leaves nothing to be desired, so the construction of Nuclear power plants never allows concrete cracking.
In addition, if cement temperature height can influence the workability of cement, produce coagulate soon, concrete slump loss is big, even easily makes cement concrete produce temperature stress, causes harm such as concrete cracking.It is higher that present large-scale new type dry kiln goes out to grind the cement temperature, adds that the depots volume is big, and the cement heat be difficult to scatter and disappear, and the cement temperature can be up to 90-100 ℃ in the storehouse, can't satisfy the requirement of nuclear power cement special temperature≤70 ℃.
For reducing the various harm that produce because of the cement temperature is higher, in cement production process, also take several steps at present and reduce mill cement temperature.Common measure has: reduce and advance to grind clinker temperature, the heat radiation of reinforcement grinding system, admixture cement grinding aid, reinforcement mill ventilation, the cooling of employing grinding mill barrel trickle etc., but the cooling efficiency of these measures all not ideal (being difficult to the cement temperature is reduced to below 85 ℃), and cost height.
In the nuclear power process of construction, in order to make unlikely generation volume change and generation thermal cracking in the mass concrete casting process, nuclear power requires the cement temperature is reduced to below 70 ℃.
Summary of the invention
The objective of the invention is to overcome the defective of prior art, a kind of nuclear island of nuclear power station dedicated high performance cement is provided, this cement can satisfy low water demand, low hydration heat (anti-cracking), the high-durability of nuclear power requirement.
Realize that the above-mentioned purpose technical scheme is as follows:
A kind of nuclear island of nuclear power station dedicated high performance cement, its batching by following weight part is formed: cement clinker 90.5%-92.0%, Wingdale blended material 4.0%-4.5%, desulfurated plaster 4.0%-5.0%;
Wherein, the cement clinker prescription is: KH=0.910 ± 0.01, SM=2.0 ± 0.1, IM=1.0 ± 0.1.
Preferably, the Al of described Wingdale blended material
2O
3≤ 2.5%.
Preferably, described cement clinker is to be prepared from through calcined by rotary kiln by raw material, and the weight part proportioning of described raw material is: Wingdale 80%-85%, sand shale 5%-10%, powdered iron ore 5%-10%.
Preferably, the control of the major ingredient of described grog is as follows: C
3S≤57.0%, C
3A≤6.0%, Cl
-≤ 0.05%, MgO≤5.0%, SO
3≤ 3.5%, f-CaO≤1.0%.
Another object of the present invention provides the preparation method of above-mentioned nuclear island of nuclear power station dedicated high performance cement.
The technical scheme that realizes above-mentioned purpose is as follows:
Prepare the method for above-mentioned nuclear island of nuclear power station dedicated high performance cement, mainly may further comprise the steps:
(1) starting material Wingdale, sand shale, powdered iron ore are prepared raw material according to proportioning through grinding;
(2) control process parameters, the calcined by rotary kiln raw material are prepared into described cement clinker; Described processing parameter control is as follows:
A) calciner temperature is 885-895 ℃;
B) rate of decomposition of raw material is 90-95%;
C) burning zone temperature is 1230-1280 ℃ in the kiln;
D) method of strong wind chilling is adopted in the grog cooling, and the cooler air quantity is 1.7-1.9Nm
3/ kgcl;
(3) grog, Wingdale blended material, desulfurated plaster adopt the grinding preparation of cement grinding mill system according to proportioning, obtain out mill cement;
(4) cement cooling, cooled temperature is lower than 70 ℃, obtains described nuclear island of nuclear power station dedicated high performance cement.
Preferably, control mill feed material fineness in the grinding process in the step (3): 80 μ m tail over＜65%, 200 μ m tails over＜55%, and 2.36mm tails over＜and 10%; The cement specific surface area that grinding is prepared is 330-360m
2/ kg.
Preferably, the cement grinding mill system is made up of pre-grinding of roll squeezer and the whole grinding of ball mill.
In cement production process of the present invention, from the raw materials and fuel quality control to raw grinding, from the formulating of recipe to the clinker burning,, produce low water demand, low hydration heat (anti-cracking), high-durability and meet Nuclear power plants high standard, the tight high-performance cement that requires to dispatching from the factory cement temperature control from cement grinding.Key point in the production process mainly comprises following four aspects:
(1) selects suitable proportion scheme and rate value, guarantee rational mineral composition
Because it is low that nuclear island of nuclear power station and conventional island concrete works require with hydration heat, the contract with dry rate of cement, require the early strength of cement stable simultaneously, later strength is high.F-CaO≤1.0% in the strict control grog; Influence the essential mineral C of hydration heat
3A and C
3The strict control of S C
3A≤6.0%, C
3S≤57%.Therefore, when the design proportion scheme, adopt lime saturation ratio KH moderate, silica modulus SM also should strictly control, and can suitably improve Fe
2O
3Content, adopt high iron formula, make aluminium-oxygen modulus control on the low side.Three rate values of grog are defined as: KH=0.910 ± 0.01, SM=2.0 ± 0.1, IM=1.0 ± 0.1.
(2) reinforcement is maintained strict control over the clinker burning pass to the management of rotary kiln
Because the change of prescription, iron level is higher, and sintering range narrows down in the clinker burning process, and the calcining difficulty during kiln temperature fluctuation, the phenomenon of burning or sintering bulk into takes place easily to give birth to.Therefore, need to adopt strict production control flow process and optimize present cement calcinating process, produce the grog of high-quality, high yield.
(3) adopt the cement grinding mill system to produce, guarantee the cement quality that dispatches from the factory
Grog, Wingdale blended material, desulfurated plaster adopt the cement special grinding system grinding of " the whole grinding of the pre-grinding of roll squeezer+ball mill " to prepare satisfactory nuclear island of nuclear power station dedicated high performance cement according to specific proportioning.Strict control mill feed material fineness in the grinding process.
(4) effectively reduce the cement temperature of dispatching from the factory
Adopt by " high-efficiency cement water cooler ", the cement temperature of will dispatching from the factory is from being reduced to below 70 ℃ more than 100 ℃.The type of cooling that this water cooler adopts " air-cooled+water-cooled " to combine, be that cement hangs down from height is past in water cooler, and cold wind and water coolant (in the closed circulation water pipe) are walked from the bottom up, carry out heat exchange by the method for a large amount of convection current, and the cement temperature is reduced rapidly.Thereby air-cooled is to adopt roots blower that cold wind is blasted to reduce the cement temperature in the water cooler, water-cooled then is by cooling circulating water convection current refrigerative method, increase the contact area of cement and water coolant, prolong the duration of contact of cement and water coolant, thereby reduce the cement temperature fast and efficiently, make the cement temperature of dispatching from the factory from being reduced to below 70 ℃ more than 100 ℃.
In sum, advantage of the present invention is:
1, reduces grog mesosilicic acid DFP (C
3A) content: the present invention adopts high iron formula, and three rate values of strict control grog are KH=0.910 ± 0.01, SM=2.0 ± 0.1, and IM=1.0 ± 0.1, thus make the grog C of production
3A content can be reduced to below 6%, satisfies the needs of nuclear power cement.
2, reduce hydration heat of cement: the hydration heat of cement that the present invention produces is lower, can reach 3 days hydration heat≤251kJ/kg of nuclear power cement fully, the requirement of 7 days hydration heat≤293kJ/kg.
3, reduce hydrated cementitious speed, avoid concrete cracking: the hydrated cementitious speed that the present invention produces is slow, can not cause excessive temperature differentials and causes concrete structure volume strain cracking.At present, ton is applied to Taishan nuclear power and Yangjiang nuclear power surplus the nuclear island of nuclear power station dedicated high performance cement 150,000 of the present invention's production, does not occur a crack so far.
4, reduce the cement temperature of dispatching from the factory: adopt by " high-efficiency cement water cooler ", the cement temperature of will dispatching from the factory reaches the requirement of nuclear power cement from successfully being reduced to below 70 ℃ more than 100 ℃.
Description of drawings
Fig. 1 is a preparation method's of the present invention schema;
Fig. 2 is the structure iron of cement cooling system.
Embodiment
Be elaborated below in conjunction with 1 pair of embodiments of the invention of accompanying drawing:
(1) proportion scheme of the described nuclear island of nuclear power station dedicated high performance of present embodiment cement is as follows:
Cement clinker 91%, Wingdale blended material 4.5%, desulfurated plaster 4.5%.Wherein the prescription of grog employing is KH:0.910 ± 0.01; SM:2.00 ± 0.1; IM:1.00 ± 0.1, grog are to be prepared from through calcined by rotary kiln by raw material, and the proportioning of preparation raw material is Wingdale 83%, sand shale 8%, powdered iron ore 9%.The Al of Wingdale blended material
2O
3≤ 2.5%.
The major ingredient control of grog is as follows: C
3S≤57.0%, C
3A≤6.0%, Cl
-≤ 0.05%, MgO≤5.0%, SO
3≤ 3.5%, f-CaO≤1.0%.
(2) preparation method of the described nuclear island of nuclear power station dedicated high performance of present embodiment cement is as follows:
1, the control of former, combustible material
The mine that raw meal proportioning presses down the Lang Tou village with Wingdale, sand shale from the Guangzhou Huadu District charcoal step that is positioned at the applicant; Ferriferous raw material mainly is from Qingyuan City, Germany and Britain's breeze of awaiting a subway.Raw coal uses the coal on ground such as Datong, Shandong and Yunnan-Guizhou.Desulfurated plaster is from the desulfurated plaster of Huangpu power plant, Zhuhai Power Plant etc., and the Wingdale blended material is from applicant's the mine that is positioned at Lang Tou village, Hua Dou district, Guangzhou charcoal step town.
Control to raw materials and fuel is as shown in the table:
2. Production Flow Chart qualifying point and control item are seen for oneself following table:
3. process control quality index table look-up
4, the grinding of raw material, homogenizing, storage
Starting material Wingdale, sand shale, powdered iron ore are prepared raw material according to above-mentioned proportioning through grinding and are entered the raw material homogenizing storehouse by lift, send in the kiln after the homogenizing in the storehouse.
5, clinker burning
The Dayao operator in time adjusts controlled variable according to going into kiln raw material quality situation and kiln condition, and the grog free calcium oxide is strict controlled in the scope.
Particularly: described processing parameter control is as follows:
A) calciner temperature is 889-891 ℃;
B) rate of decomposition of raw material is 93-94%;
C) burning zone temperature is 1250-1260 ℃ in the kiln;
D) method of strong wind chilling is adopted in the grog cooling, and the cooler air quantity is 1.8Nm3/kgcl.
6, grog stores
According to the requirement of producting rule, the special storehouse of using storage capacity to reach 50,000 tons stores grog.Because storage capacity is big, can make grog obtain sufficient homogenizing, also can tentatively cool off simultaneously grog, help to reduce the cement temperature.
7, manufacture of cement and storage vault
Use satisfactory grog, gypsum, Wingdale blended material, adopt the cement grinding mill system grinding of forming by the whole grinding of the pre-grinding of roll squeezer+ball mill to prepare satisfactory nuclear island of nuclear power station dedicated high performance cement according to said ratio.
In the grinding process strict control mill feed material fineness promptly 80 μ m tail over＜65%, 200 μ m tails over＜55%, 2.36mm tails over＜10%; The cement specific surface area that grinding is prepared is controlled at 330-360m2/kg.
8, go out to grind the cement cooling
Adopt the high-efficiency cement cooling system, with the cement temperature from being reduced to below 70 ℃ more than 100 ℃.The type of cooling that this cooling system adopts " air-cooled+water-cooled " to combine, be that cement hangs down from height is past in the cement cylinder, and cold wind and water coolant (in the closed circulation water pipe) are walked from the bottom up, method by a large amount of convection current is carried out heat exchange, the cement temperature is reduced rapidly, and the structure of cement cooling system is referring to Fig. 2.
The cement cooling system comprises cement cylinder 1, cement cylinder 1 is provided with cement import 2 and cement exit 3, cement import 2 is positioned at the top of cement cylinder 1, cement exit 3 is positioned at the bottom of cement cylinder 1, be provided with cooling water pipeline 4 in the inside of cement cylinder 1, be provided with spray water pipeline 5 in the outside of cement cylinder 1, cooling water pipeline 4 and spray water pipeline 5 all communicate with water-in; Also be provided with suction port 6, bottom on the top of cement cylinder 1 and also be provided with blast inlet 7, suction port 6 communicates with suction cleaner 19, and blast inlet 7 communicates with blower fan 15.Wherein, also include cement transfer lime 8, water inlet pipe 10, return water pipe 12, valve 16, worm conveyor 18 and cement wagon spout 17; The bottom of cement transfer lime 8 is a cement inlet 9, and the upper end of cement transfer lime 8 communicates with described cement import 2; Be provided with water pump 11 on water inlet pipe 10, the import of described cooling water pipeline 4 and spray water pipeline 5 communicates with water inlet pipe 10; Bottom at described cement cylinder 1 outer wall also is provided with water leg 13, and this water leg 13, described cooling water pipeline 4 all communicate with return water pipe 12.The bottom of described cement cylinder 1 is back taper, is provided with ventilating groove 14 on the conical surface of cement cylinder 1, and described blast inlet 7 communicates with described cement cylinder 1 by this ventilating groove 14.Described blower fan 15 is a positive displacement blower fan 15.Valve 16 is located at described cement exit 3 places, and described cement exit 3 is positioned at the top of first end of worm conveyor 18, and cement wagon spout 17 is positioned at the below of second end of worm conveyor 18.
In the cement process of cooling, cement falls from top to bottom from cement cylinder 1 under action of gravity, and cooling air upwards forms cooling draught from the bottom of cement cylinder 1, and suction cleaner 19 carries out dust suction from the suction port 6 on cement cylinder 1 top; Water coolant enters cooling water pipeline 4 and spray water pipeline 5 under the effect of water pump 11, from the inside and the outside of cement cylinder 1 cement cylinder 1 is cooled off respectively, temperature raises after water coolant and the cement heat exchange, the temperature of cement is from being reduced to more than 100 ℃ below 70 ℃, and the higher water of temperature reclaims through return water pipe 12.Because adopt air cooling, water-cooled mode simultaneously, and water-cooled is divided into inner cooling and outer wall refrigerative mode, the type of cooling is more, heat interchanging area is big, the heat exchange efficiency height, and cooling performance is better.
Available dedicated cement silo (3# storehouse) stores satisfactory cement (specific targets of cement see Table 1 and table 2).
The nuclear island of nuclear power station dedicated high performance cement physics of present embodiment preparation, the requirement that mechanical property must meet table 1, the main content controlling index of the objectionable constituent of cement and grog sees Table 2.
Physics, the mechanical property of table 1 nuclear island of nuclear power station dedicated high performance cement
The objectionable constituent of table 2 cement and grog mainly contain scale
Embodiment 2
(1) proportion scheme of the described nuclear island of nuclear power station dedicated high performance of present embodiment cement is as follows:
Cement clinker 90.5%, Wingdale blended material 4.5%, desulfurated plaster 5.0%.Wherein the prescription of grog employing is KH:0.910 ± 0.01; SM:2.00 ± 0.1; IM:1.00 ± 0.1, grog are to be prepared from through calcined by rotary kiln by raw material, and the proportioning of preparation raw material is Wingdale 85%, sand shale 10%, powdered iron ore 5%.The Al of Wingdale blended material
2O
3≤ 2.5%.
The major ingredient control of grog is as follows: C
3S≤57.0%, C
3A≤6.0%, Cl
-≤ 0.05%, MgO≤5.0%, SO
3≤ 3.5%, f-CaO≤1.0%.
(2) preparation method of the described nuclear island of nuclear power station dedicated high performance of present embodiment cement is as follows:
1, the control such as the embodiment 1 of former, combustible material.
2, Production Flow Chart qualifying point and control project such as embodiment 1.
3, process control quality index such as embodiment 1.
4, the grinding of raw material, homogenizing, storage such as embodiment 1.
5, clinker burning
Described processing parameter control is as follows:
A) calciner temperature is 885-889 ℃;
B) rate of decomposition of raw material is 93.5-95%;
C) burning zone temperature is 1270-1280 ℃ in the kiln;
D) method of strong wind chilling is adopted in the grog cooling, and the cooler air quantity is 1.7Nm3/kgcl.
6, grog stores as embodiment 1.
7, manufacture of cement and storage vault
Use satisfactory grog, gypsum, Wingdale blended material, adopt the cement grinding mill system grinding of forming by the whole grinding of the pre-grinding of roll squeezer+ball mill to prepare satisfactory nuclear island of nuclear power station dedicated high performance cement according to said ratio.
In the grinding process strict control mill feed material fineness promptly 80 μ m tail over＜65%, 200 μ m tails over＜55%, 2.36mm tails over＜10%; The cement specific surface area that grinding is prepared is controlled at 330-360m
2/ kg.
8, go out to grind the cement cooling, as embodiment 1.Obtain described nuclear island of nuclear power station dedicated high performance cement.
The performance such as the embodiment 1 of the described nuclear island of nuclear power station dedicated high performance cement that present embodiment is prepared into.
Embodiment 3
(1) proportion scheme of the described nuclear island of nuclear power station dedicated high performance of present embodiment cement is as follows:
Cement clinker 92%, Wingdale blended material 4.0%, desulfurated plaster 4.0%.Wherein the prescription of grog employing is KH:0.910 ± 0.01; SM:2.00 ± 0.1; IM:1.00 ± 0.1, grog are to be prepared from through calcined by rotary kiln by raw material, and the proportioning of preparation raw material is Wingdale 80%, sand shale 10%, powdered iron ore 10%.The Al of Wingdale blended material
2O
3≤ 2.5%.
The major ingredient control of grog is as follows: C
3S≤57.0%, C
3A≤6.0%, Cl
-≤ 0.05%, MgO≤5.0%, SO
3≤ 3.5%, f-CaO≤1.0%.
(2) preparation method of the described nuclear island of nuclear power station dedicated high performance of present embodiment cement is as follows:
1, the control such as the embodiment 1 of former, combustible material.
2, Production Flow Chart qualifying point and control project such as embodiment 1.
3, process control quality index such as embodiment 1.
4, the grinding of raw material, homogenizing, storage such as embodiment 1.
5, clinker burning
Described processing parameter control is as follows:
A) calciner temperature is 890-895 ℃;
B) rate of decomposition of raw material is 90-93%;
C) burning zone temperature is 1230-1250 ℃ in the kiln;
D) method of strong wind chilling is adopted in the grog cooling, and the cooler air quantity is 1.9Nm
3/ kgcl.
6, grog stores as embodiment 1
7, manufacture of cement and storage vault
Use satisfactory grog, gypsum, Wingdale blended material, adopt the cement grinding mill system grinding of forming by the whole grinding of the pre-grinding of roll squeezer+ball mill to prepare satisfactory nuclear island of nuclear power station dedicated high performance cement according to said ratio.
In the grinding process strict control mill feed material fineness promptly 80 μ m tail over＜65%, 200 μ m tails over＜55%, 2.36mm tails over＜10%; The cement specific surface area that grinding is prepared is controlled at 330-360m2/kg.
8, go out to grind the cement cooling, as embodiment 1.Obtain described nuclear island of nuclear power station dedicated high performance cement.
The performance such as the embodiment 1 of the described nuclear island of nuclear power station dedicated high performance cement that present embodiment is prepared into.
Be specific embodiments of the invention only below, do not limit protection scope of the present invention with this; Any replacement and the improvement done on the basis of not violating the present invention's design all belong to protection scope of the present invention.
Claims (7)
1. a nuclear island of nuclear power station dedicated high performance cement is characterized in that, its batching by following weight part is formed: cement clinker 90.5%-92.0%, Wingdale blended material 4.0%-4.5%, desulfurated plaster 4.0%-5.0%; Wherein, the cement clinker prescription is: KH=0.910 ± 0.01, SM=2.0 ± 0.1, IM=1.0 ± 0.1.
2. nuclear island of nuclear power station dedicated high performance cement according to claim 1, it is characterized in that, described cement clinker is to be prepared from through calcined by rotary kiln by raw material, and the weight part proportioning of described raw material is: Wingdale 80%-85%, sand shale 5%-10%, powdered iron ore 5%-10%.
3. nuclear island of nuclear power station dedicated high performance cement according to claim 2 is characterized in that, the major ingredient control of described grog is as follows: C
3S≤57.0%, C
3A≤6.0%, Cl
-≤ 0.05%, MgO≤5.0%, SO
3≤ 3.5%, f-CaO≤1.0%.
4. according to each described nuclear island of nuclear power station dedicated high performance cement of claim 1-3, it is characterized in that the Al of described Wingdale blended material
2O
3≤ 2.5%.
5. a method for preparing each described nuclear island of nuclear power station dedicated high performance cement of claim 1-4 is characterized in that, mainly may further comprise the steps:
(1) starting material Wingdale, sand shale, powdered iron ore are prepared raw material according to proportioning through grinding;
(2) control process parameters, the calcined by rotary kiln raw material are prepared into described cement clinker; Described processing parameter control is as follows:
A) calciner temperature is 885-895 ℃;
B) rate of decomposition of raw material is 90-95%;
C) burning zone temperature is 1230-1280 ℃ in the kiln;
D) method of strong wind chilling is adopted in the grog cooling, and the cooler air quantity is 1.7-1.9Nm
3/ kgcl;
(3) grog, Wingdale blended material, desulfurated plaster adopt the grinding preparation of cement grinding mill system according to proportioning, obtain out mill cement;
(4) cement cooling, cooled temperature is lower than 70 ℃, obtains described nuclear island of nuclear power station dedicated high performance cement.
6. preparation method according to claim 5 is characterized in that, control mill feed material fineness in the grinding process in the step (3): 80 μ m tail over＜65%, 200 μ m tails over＜55%, and 2.36mm tails over＜and 10%; The cement specific surface area that grinding is prepared is 330-360m
2/ kg.
7. preparation method according to claim 5 is characterized in that, the cement grinding mill system is made up of pre-grinding of roll squeezer and the whole grinding of ball mill.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201110151123 CN102285769A (en) | 2011-06-07 | 2011-06-07 | Special high-performance cement for nuclear island and preparation method thereof |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN 201110151123 CN102285769A (en) | 2011-06-07 | 2011-06-07 | Special high-performance cement for nuclear island and preparation method thereof |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN102285769A true CN102285769A (en) | 2011-12-21 |
Family
ID=45332551
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN 201110151123 Pending CN102285769A (en) | 2011-06-07 | 2011-06-07 | Special high-performance cement for nuclear island and preparation method thereof |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN102285769A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106746782A (en) * | 2016-12-12 | 2017-05-31 | 中国建筑材料科学研究总院 | Nuclear power low-heat cement and preparation method thereof |
| CN115043604A (en) * | 2022-07-15 | 2022-09-13 | 中国建筑材料科学研究总院有限公司 | Preparation method of low-background cement and low-background cement |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1810696A (en) * | 2006-01-18 | 2006-08-02 | 内蒙古西水创业股份有限公司 | Freeze-thaw resisting cement and its production process |
| CN101386480A (en) * | 2008-10-15 | 2009-03-18 | 华南理工大学 | Method for producing portland cement clinker using domestic waste incineration residue |
-
2011
- 2011-06-07 CN CN 201110151123 patent/CN102285769A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1810696A (en) * | 2006-01-18 | 2006-08-02 | 内蒙古西水创业股份有限公司 | Freeze-thaw resisting cement and its production process |
| CN101386480A (en) * | 2008-10-15 | 2009-03-18 | 华南理工大学 | Method for producing portland cement clinker using domestic waste incineration residue |
Non-Patent Citations (1)
| Title |
|---|
| 《新世纪水泥导报》 20021231 唐声飞 等 核电站主体工程用水泥的生产 51-52 1-7 , 第04期 * |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106746782A (en) * | 2016-12-12 | 2017-05-31 | 中国建筑材料科学研究总院 | Nuclear power low-heat cement and preparation method thereof |
| CN106746782B (en) * | 2016-12-12 | 2019-05-31 | 中国建筑材料科学研究总院 | Nuclear power low-heat cement and preparation method thereof |
| CN115043604A (en) * | 2022-07-15 | 2022-09-13 | 中国建筑材料科学研究总院有限公司 | Preparation method of low-background cement and low-background cement |
| US20240018048A1 (en) * | 2022-07-15 | 2024-01-18 | China Building Materials Academy Co., Ltd. | Method for preparing low-background cement |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN101786811B (en) | Method for preparing multicomponent powder binding material | |
| CN103964713B (en) | Flyash and Bayer process red mud is utilized to prepare the method for belite aluminosulfate cement | |
| CN103159450B (en) | Production method of foamed concrete block manufactured from steel slag | |
| CN108821671B (en) | Full-industrial solid waste high-strength ready-to-use foamed concrete material and preparation method thereof | |
| CN108892401B (en) | Method for calcining belite sulphoaluminate cement clinker by using phosphogypsum and cement clinker | |
| CN103864320B (en) | Low heat portland blast-furnace-slag cement and production method thereof | |
| CN112851284A (en) | Gypsum self-leveling mortar for ground heating backfill and preparation method thereof | |
| CN104556909B (en) | A kind of be raw material with flyash fast solidifying anti-corrosion cement and preparation method thereof | |
| CN103819217B (en) | The air-entrained concrete building block that a kind of dump leaching slag is produced | |
| CN104129933B (en) | A kind of nuclear power cement utilizing copper scrap slag obtained and preparation method thereof | |
| CN105016642A (en) | Environment-friendly and energy-saving steel slag water permeable brick and preparation method thereof | |
| CN102976642B (en) | Special silicate cement for nuclear power and production method thereof | |
| CN109809720A (en) | Special cement for waterproof mortar and preparation method thereof | |
| CN112939494A (en) | High-magnesium cement and preparation method thereof | |
| CN104402259B (en) | The manufacture method of the anti-contraction hydraulic cementing materials of a kind of radioresistance | |
| CN104129932B (en) | A kind of high-strength middle thermonuclear electrical engineering cement special and preparation method thereof | |
| CN103466968B (en) | Method for preparing natural hydraulic lime with lead and zinc mine tailings | |
| CN105801062B (en) | The method that self-leveling material is prepared using phosphorus solid waste | |
| CN105000814A (en) | Processing method for preparing fast-hardening early-strength oil well cement with industrial waste slag | |
| CN104030585B (en) | The method of clinker is made of sludge | |
| CN104016601A (en) | Method for producing cement cementing material through industrial waste residue sludge | |
| CN101417867B (en) | Method for preparing silicate magnesium slag concrete by using magnesium slag | |
| CN102285769A (en) | Special high-performance cement for nuclear island and preparation method thereof | |
| CN111960703A (en) | Preparation process of modified steel slag micro powder, and modified steel slag micro powder and concrete prepared by preparation process | |
| CN106746782A (en) | Nuclear power low-heat cement and preparation method thereof |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C12 | Rejection of a patent application after its publication | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20111221 |