CN104294181A - Low-alloy steel - Google Patents
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Abstract
The invention discloses low-alloy steel. The low-alloy steel comprises the following components in percentage by mass: 0.16-0.22% of C, 0.10-0.30% of Si, 1.20-1.60% of Mn, less than 0.008% of P, less than 0.005% of S, less than 0.15% of Cr, 0.50-0.80% of Ni, 0.43-0.57% of Mo, less than 0.01% of V, less than 0.08% of Cu, less than 0.04% of Al, less than 0.03% of Co, less than 0.010% of As, less than 0.010% of Sn, less than 0.002% of Sb, less than 0.0005% of B, less than 0.8 ppm of H, and the balance of Fe. The low-alloy steel has the advantages of low radiation sensibility, excellent radiation embrittlement resistance and long service life.
Description
Technical field
The present invention relates to the low alloy steel that a kind of radiation sensitivity is low.Low alloy steel of the present invention is applicable to manufacture reactor pressure vessel.
Background technology
Reactor pressure vessel is one of key equipment of PWR nuclear power plant, and its main security function is: hold the core components of reactor, in-pile component and In-core Instrumentation parts; Supporting reactor control rod driving mechanism and other heap roof construction parts; The pressure boundary of anabolic reaction reactor coolant system; Construct the important barrier of second of nuclear island core activity safety precaution.Due to non-exchange in its phase in longevity, thus the reliability of reactor pressure vessel is the key factor determining the PWR nuclear power plant life-span.Along with the development of nuclear industry, improve the economy of nuclear power plant and to be inevitable development trend, therefore the enhancing of reactor pressure vessel life-time dilatation and reliability is the key ensureing that nuclear power plant runs the long-lived phase.
Reactor pressure vessel works for a long time under high dosage irradiation environment.Therefore, usually require that the material for the manufacture of reactor pressure vessel possesses lower radiation sensitivity and lower initial nil ductility temperature (Initial R T
nDT).
Current, the material for the manufacture of reactor pressure vessel is mainly 16MND5, but the content of radiation sensitive element is wherein still higher, and initial nil ductility temperature (Initial R T
nDT) higher, constrain the work-ing life of reactor pressure vessel, its work-ing life is generally about 40 years.
Summary of the invention
Namely object of the present invention is the low alloy steel providing low, the resistance to radiation embrittlement superior performance of a kind of radiation sensitivity and long service life.
In order to achieve the above object, contriver, for 16MND5, has studied the wherein chemical impact organized low alloy steel radiation sensitivity and initial nil ductility temperature in great detail.As a result, opinion new is as follows obtained:
1.Mn and Ni can increase γ phase, crystal grain thinning, raising hardening capacity, improves the over-all properties of steel.The easy chemical combination of Ni and S in thermal environment, crystal boundary is formed the NiS reticulattion of low melting point and produces hot-short, when Ni content higher than 0.8% time hot-short degree progressively strengthen, therefore must control Ni upper content limit.Cr and Mo can improve hardening capacity, the reduction nil ductility temperature of steel.After irradiation, the Cr atom of solid solution can catch C atom and atom N freely, reduces interstitial atom to the impact of irradiation.Mo can reduce temper brittleness, obviously suppresses radiation embrittlement, and the Mo in matrix has the effect of the impurity atoms segregations such as control P, S, but Mo too high levels then causes the reduction of Mo content in matrix, and therefore Mo content must control.V can crystal grain thinning, improve intensity, the toughness of steel, but V is the element to radiation sensitivity evil, not only produce radiation embrittlement, during irradiation, the Carbide Precipitation of V can cause embrittlement equally.The increase of V content easily causes welded heat affecting zone brittle, adds the thermal crack susceptibility of steel.Therefore must control V upper content limit.
2.Co generates radio isotope by after neutron irradiation
60co, generates after continuing decay
60ni, and radiate the gamma-rays to human body serious harm, therefore must strict control Co content.The isotropic substance of B
10b has very large neutron-absorption cross-section, radiation embrittlement can be caused obviously to aggravate in steel containing B, needs strict its content of control.Si has the effect of constant illumination defect, and along with irradiation temperature increases, can reduce the self-healing ability of point defect, irradiation effect increases thereupon.Therefore, Si too high levels can cause the radiation sensitivity of low alloy steel to improve, and therefore its content is unsuitable higher.P and S not only reduces the plasticity of steel, and has the tendency accelerating radiation embrittlement, strictly must control, reduces its content as far as possible.
3.Cu is very large on radiation embrittlement impact, its reason be in low alloy steel material remaining Cu content much larger than when 300 DEG C 0.002% solubleness, irradiation energy makes the precipitation of Cu improve several order of magnitude simultaneously.The Micro-v oid that the free Cu centering substring level collision be settled out produces has stabilization, and Micro-v oid is the major reason of radiation embrittlement.Irradiation can accelerate to produce the small rich Cu precipitation containing Ni and Mn, and they cause embrittlement and the embrittlement of material because hindering dislocation motion.
Ni is the effective element expanding austenite phase, crystal grain thinning, spheroidized carbide and guarantee over-all properties and improve hardening capacity.But test shows that the height of Ni on the impact of material irradiation embrittlement and Cu content and fast neutron fluence is closely related.Ni and Cu has the effect of mutually promoting.When Cu content is lower, Ni is less to irradiation hazard; When Cu content is higher, Ni is larger to irradiation hazard.Same when Ni content is higher, Cu is also larger on irradiation impact.It is relevant that the two complementary phenomenon same Ni, Cu and room form the complicated defect in more stable Cu-Ni-room.The Rational Composition coupling of Ni and Cu obviously can reduce irradiation effect, and namely Ni content is unsuitable too high, and Cu content should be as far as possible low.
P is relevant in the segregation of crystal boundary with P on the impact of radiation embrittlement.P atomic diffusion presents a large amount of enrichments of P, Ni, Mn to crystal boundary, causes segregation that boundary surfaces can be reduced, thus makes initial nil ductility temperature (Initial R T
nDT) raise, strengthen the radiation embrittlement degree of material.P is relevant with Cu content on the impact of radiation embrittlement simultaneously, and when Cu is lower, the P atom group and the phosphide precipitation that are gathered into several nanosized are many, therefore show P very sensitive to irradiation; When Cu content height, P is bonded in rich Cu precipitation, produces copper phosphide, and the independent impact of P increases along with Cu and has been lowered.
S easily and Mn and Fe react FeS and MnS generating low melting point, add the fragility of low alloy steel material and reduce maximum impact merit, thus upper mounting plate energy is reduced.
Based on above-mentioned analysis, the interaction of Cu and Ni and P is the least favorable factor of the irradiation behaviour affecting low alloy steel.Ni is the alloying element in steel, when suitably increasing Ni to improve the toughness of steel, adjoint must fall low content of Cu, in order to avoid irradiation effect increase; And Cu content low time P harm increase, therefore should reduce P content simultaneously.
The present invention completes based on above-mentioned opinion, and it will be intended to following low alloy steel.
A kind of low alloy steel, by percentage to the quality, its composition is: C:0.16 ~ 0.22%, Si:0.10 ~ 0.30%, Mn:1.20 ~ 1.60%, below P:0.008%, below S:0.005%, below Cr:0.15%, Ni:0.50 ~ 0.80%, Mo:0.43 ~ 0.57%, below V:0.01%, below Cu:0.08%, below Al:0.04%, below Co:0.03%, below As:0.010%, below Sn:0.010%, below Sb:0.002%, below B:0.0005%, below H:0.8ppm, all the other compositions are Fe.
As optimization, wherein the mass percent of P is below 0.006%, and the mass percent of Cu is below 0.05%, and the mass percent of B is below 0.0003%.
As further optimization, a kind of low alloy steel, by percentage to the quality, its composition is: C:0.18%, Si:0.18%, Mn:1.36%, P:0.005%, S:0.002%, Cr:0.12%, Ni:0.75%, Mo:0.48%, V:0.004%, Cu:0.02%, Al:0.007%, Co:0.02%, As:0.002%, Sn:0.002%, Sb:0.0007%, B:0.0002%, H:0.6ppm, all the other compositions are Fe.
As further optimization, a kind of low alloy steel, by percentage to the quality, its composition is: C:0.17%, Si:0.19%, Mn:1.40%, P:0.005%, S:0.002%, Cr:0.12%, Ni:0.71%, Mo:0.48%, V:0.01%, Cu:0.02%, Al:0.01%, Co:0.02%, As:0.002%, Sn:0.002%, Sb:0.0007%, B:0.0002%, H:0.8ppm, all the other compositions are Fe.
Advantage of the present invention and beneficial effect are:
Low alloy steel of the present invention, when reactor core irradiation, also can realize the unapproachable low radiation sensitivity of low alloy steel (as 16MND5) in the past and low initial nil ductility temperature (Initial R T
nDT), the brittle ability of Flouride-resistani acid phesphatase is strong.Therefore, the present invention is used for reactor pressure vessel, effectively can improves the work-ing life of reactor pressure vessel, make reach more than 60 years the work-ing life of reactor pressure vessel.
Embodiment
The chemical constitution describing low alloy steel of the present invention in detail is defined as the reason of above-mentioned scope below.In addition, in the following description, as long as no being particularly limited to, " % " expression " mass percent ".
C：0.16～0.22%
C is the principal element realizing requirement of strength, content higher than 0.16% time guarantee material possess enough intensity.
Meanwhile, because C belongs to clearance type atom, increase C content and will make toughness decline, nil ductility temperature rising, the high welding to low alloy steel of C content simultaneously also has disadvantageous effect, and therefore under the prerequisite of proof strength, C content should lower than 0.22%.
Si：0.10～0.30%
Si has the effect of strengthening matrix, and simultaneously because bring into from the pig iron raw material when Si smelts, it is rational for therefore controlling its content higher than 0.10%.
On the other hand, Si content higher than 0.30%, then can be harmful to irradiation, because Si has the effect of constant illumination defect, when Elevated temperature irradiation, can hinder the restorability of point defect and derivative radiation defect thereof, and its content is unsuitable higher.Therefore, Si content is made to be 0.10 ~ 0.30%.
Mn：1.20～1.60%
Mn can increase γ phase, crystal grain thinning, raising hardening capacity, improves the over-all properties of steel.The effect improving steel over-all properties lower than 1.20%, Mn as Mn content is not obvious.
Mn can facilitate P and other impurity atoms to produce segregation in original austenite crystal prevention while raising hardening capacity and strengthening matrix, if Mn content is higher than 1.60%, can reduce crystal boundary force of cohesion, increase temper brittleness.
Ni：0.50～0.80%
Ni can increase γ phase, crystal grain thinning, raising hardening capacity, improves the over-all properties of steel.If the effect that the content of Ni improves steel over-all properties lower than 0.50%, Ni is not obvious.
On the other hand, the easy chemical combination of Ni and S in thermal environment, crystal boundary is formed the NiS reticulattion of low melting point and produces hot-short, when Ni content higher than 0.8% time hot-short degree progressively strengthen.Therefore, Ni content is made to be 0.50 ~ 0.80%.
Below Cu:0.08%
Ni is the effective element expanding austenite phase, crystal grain thinning, spheroidized carbide and guarantee over-all properties and improve hardening capacity.But test shows that the height of Ni on the impact of material irradiation embrittlement and Cu content and fast neutron fluence is closely related.Ni and Cu has the effect of mutually promoting.When Cu content is lower, Ni is less to irradiation hazard; When Cu content is higher, Ni is larger to irradiation hazard.Same when Ni content is higher, Cu is also larger on irradiation impact.It is relevant that the two complementary phenomenon and Ni, Cu and room form the complicated defect in more stable Cu-Ni-room.The Rational Composition coupling of Ni and Cu obviously can reduce irradiation effect, and namely Ni content is unsuitable too high, and Cu content should be as far as possible low.Therefore, Cu content is below 0.08%, and irradiation effect, 0.50 ~ 0.80%, can, on the basis ensureing low alloy steel over-all properties, reduce minimum by the content of Ni.
In addition, for the present invention for core region, the content of Cu is preferably less than 0.05%.
Below P:0.008%
P is relevant in the segregation of crystal boundary with P on the impact of radiation embrittlement.P atomic diffusion presents a large amount of enrichments of P, Ni, Mn to crystal boundary, causes segregation that boundary surfaces can be reduced, thus makes Initial R T
nDTraise, strengthen the radiation embrittlement degree of material.P is relevant with Cu content on the impact of radiation embrittlement simultaneously, and when Cu is lower, the P atom group and the phosphide precipitation that are gathered into several nanosized are many, therefore show P very sensitive to irradiation; When Cu content height, P is bonded in rich Cu precipitation, produces copper phosphide, and the independent impact of P increases along with Cu and has been lowered.
Based on above-mentioned analysis, the interaction of Cu and Ni and P is the least favorable factor of the irradiation behaviour affecting low alloy steel.Ni is the alloying element in steel, when suitably increasing Ni to improve the toughness of steel, adjoint must fall low content of Cu, in order to avoid irradiation effect increase; And Cu content low time P harm increase, therefore should reduce P content simultaneously.Therefore, Cu content is below 0.08%, P content is less than 0.008%, can reduce the radiation sensitivity of low alloy steel as far as possible.Meanwhile, excessively reduce P content and cost can be caused significantly to rise, this is also by the Another reason of P content restriction less than 0.008%.
In addition, for the present invention for core region, the content of P is preferably less than 0.006%.
Below S:0.005%
S easily and Mn and Fe react FeS and MnS generating low melting point, add the fragility of low alloy steel material and reduce maximum impact merit, thus the upper mounting plate Energy value (platform energy value: in shock absorption energy temperature curve, the absorption energy that upper shelf region is corresponding) of reflection toughness of material is reduced.The content of S should be more few better, and consider that excessively reducing S content can cause cost significantly to rise, therefore S content is less than 0.005%.
Below Cr:0.15%
Cr can improve hardening capacity, the reduction ductility transition temperature of steel.After irradiation, the Cr atom of solid solution can catch C atom and atom N freely, reduces interstitial atom to the impact of irradiation.
Cr and Mn and Mo can form alloyed cementite and increase matrix strength, and from this alloying constituent angle analysis, the control for Cr content should consider the impact of Mn and Mo content; And Cr has disadvantageous effect to weldability and under built up welding clad crack susceptibility, therefore must control its content is less than 0.15%.
Mo：0.43～0.57%
Mo can reduce temper brittleness, obviously suppresses radiation embrittlement, and the Mo in matrix has the effect of the impurity atoms segregations such as control P, S, but Mo too high levels can cause the reduction of Mo content in matrix on the contrary, and therefore Mo content controls 0.43 ~ 0.57%.Both can play the effect suppressing radiation embrittlement, also can play the effect of the impurity atoms segregations such as control P, S.
Below V:0.01%
V can crystal grain thinning, improve intensity, the toughness of steel, but V is the element harmful to irradiation, not only produce radiation embrittlement, during irradiation, the Carbide Precipitation of V can cause embrittlement equally.The increase of V content easily causes welded heat affecting zone brittle, adds the thermal crack susceptibility of steel.For the object improving the resistance to radiation embrittlement performance of the present invention, therefore require that V content is below 0.01%.
Below Co:0.03%
Co generates radionuclide by after neutron irradiation
60co, generates after continuing decay
60ni, and radiate the gamma-rays to human body serious harm.If Co content is greater than 0.03%, the gamma-rays dosage of generation is excessive, and limiting Co content is less than 0.03%.
Below B:0.0005%
The isotropic substance of B
10b has very large neutron-absorption cross-section, radiation embrittlement can be caused obviously to aggravate in steel containing B.Therefore, the resistance to radiation embrittlement performance of considering cost, is limited to less than 0.0005% by the content of B.
In addition, for the present invention for core region, the content of B is preferably less than 0.0003%.
Below Al:0.04%
Below As:0.010%
Below Sn:0.010%
Below Sb:0.002%
Below H:0.8ppm
Although Al, As, Sn and Sb element content in steel is little, comparatively large to irradiation behaviour especially Elevated temperature irradiation performance impact, therefore in order to reduce the impact of irradiation on material property, the strict content controlling above-mentioned residual element as far as possible.
The too high meeting of H content causes hydrogen embrittlement, and the intensity of steel and toughness are reduced, and is the major cause producing white point, the too high irradiation behaviour to material of H content also has disadvantageous effect simultaneously.
Embodiment:
Preparation technology's flow process of the present invention is as follows:
Adopt electric furnace slightly to make steel water, then continue refined molten steel in a vacuum furnace, next step adopts vacuum casting process, controls the add-on of each component, the content of minimizing harmful element and impurity.The steel ingot of cast forges on super large forging press, controls final forging temperature and be not less than 850 DEG C in forging process, and through time forging of many fire, total forging ratio of forging is not less than 3.In order to improve forging interior tissue and grain fineness number, reduce H content further, forging experiences the normalizing treatment of 900 DEG C-980 DEG C after forging, the temper of 600 DEG C-700 DEG C.In order to obtain high performance forging before property heat treatment, forging stock is machined to as far as possible close to completion profile.After this forging experiences the quench treatment of 850 DEG C-925 DEG C, and the temper of 635 DEG C-665 DEG C.If when every result such as nondestructive test and performance test all meets the demands, forging carries out final precision work, and so far material completes manufacture.
In embodiments of the invention (No1 ~ No3), the content of each component is as shown in table 1.In table 1, the content of each component is mass percent.
Table 1
For ensureing that low alloy steel there will not be brittle rupture, reference nil-ductility transition temperature (RT within the phase in whole service longevity
nDT) be very important performance assessment criteria.The RT in the usual end of term in employing following formula Calculating material longevity
nDT:
ART=Initial R T
nDT+ Δ RT
nDT+ M
In formula: ART is the RT in the end of term in longevity
nDT, the RT after namely changing through irradiation
nDT; Δ RT
nDTfor RT
nDTknots modification; M is safety allowance.As can be seen from above formula, when safety allowance is certain, ART depends on Initial R T
nDTwith Δ RT
nDT.
Initial R T
nDTvalue is obtained by the performance test of material.
Test method is as follows:
(1) first NDT is measured, at T by the drop weight test of GB/T 6803
nDTthe summer making one group of three sample at+33 DEG C of temperature than V-type shock test, when shock absorption energy all>=68J, side expansion all>=0.89mm time, confirm T
nDTbe exactly RT
nDT.
(2) when above-mentioned requirements does not meet, can higher than T
nDTdoing supplementary test at+33 DEG C of temperature, is one group with three samples, each improve 5 DEG C and tests, until three samples all meet the temperature T of above-mentioned requirements
cVtill.Now RT
nDT=T
cV-33 DEG C, the Initial R T of material can be obtained thus
nDT.
In No1 ~ No4, Initial R T
nDTbe worth as shown in table 2.No4 represents the comparative example that existing 16MND5 is formed.
Table 2
Another variable Δ RT
nDTbe draw according to formulae discovery, calculation formula mainly considers two aspects: one is the accumulation fast neutron fluence of material, and two is the radiation sensitive elements in material, based on this by experimental formula that matching testing data draws.
The foundation of RG 1.99 calculation formula of the U.S. considers the impact of Cu and Ni:
In formula: [CF] is chemokines, can table look-up according to Cu and Ni content and obtain; F is fast neutron fluence (E>1Mev), unit 10
19n/cm
2.
France's RCC-M ZG6120 calculation formula considers the impact of Cu and P:
In formula: f is fast neutron fluence (E>1Mev), unit n/cm
2; %Cu is the content of Cu, and when Cu<0.08%, value is 0.08; %P is the content of P, and when P<0.008%, value is 0.008.
FIM and the FIS formula of France RSEM is all considered Cu, P and Ni three:
In formula: f is fast neutron fluence (E>1Mev), unit n/cm
2; Cu, Ni, P content is weight percentage, and when when Cu<0.08%, value is 0.08, P<0.008%, value is 0.008.
Can reach a conclusion according to above formula, when fast neutron fluence one timing, Cu, Ni, P content is lower, Δ RT
nDTlower, then ART is also lower.
The end of term in reactor pressure vessel longevity internal surface accumulation fast neutron fluence peak value is with 7.69 × 10
19n/cm
2count that (40 years, stressor: 75%), substituted into above-mentioned various formulae discovery Δ RT by the radiation sensitive constituent content value in table 1
nDT, then with Initial R T
nDTsummation draws ART, and result is as shown in table 3.
Table 3
As can be seen from Table 3, the ART of the embodiment of the present invention is starkly lower than the ART of comparative example.Low alloy steel radiation sensitivity of the present invention is low, long service life.
Claims (4)
1. a low alloy steel, is characterized in that, by percentage to the quality, its composition is: C:0.16 ~ 0.22%, Si:0.10 ~ 0.30%, Mn:1.20 ~ 1.60%, below P:0.008%, below S:0.005%, below Cr:0.15%, Ni:0.50 ~ 0.80%, Mo:0.43 ~ 0.57%, below V:0.01%, below Cu:0.08%, below Al:0.04%, below Co:0.03%, below As:0.010%, below Sn:0.010%, below Sb:0.002%, below B:0.0005%, below H:0.8ppm, all the other compositions are Fe.
2. a kind of low alloy steel according to claim 1, is characterized in that; The mass percent of P is below 0.006%, and the mass percent of Cu is below 0.05%, and the mass percent of B is below 0.0003%.
3. a kind of low alloy steel according to claim 1, is characterized in that, by percentage to the quality, its composition is: C:0.18%, Si:0.18%, Mn:1.36%, P:0.005%, S:0.002%, Cr:0.12%, Ni:0.75%, Mo:0.48%, V:0.004%, Cu:0.02%, Al:0.007%, Co:0.02%, As:0.002%, Sn:0.002%, Sb:0.0007%, B:0.0002%, H:0.6ppm, all the other compositions are Fe.
4. a kind of low alloy steel according to claim 1, is characterized in that, by percentage to the quality, its composition is: C:0.17%, Si:0.19%, Mn:1.40%, P:0.005%, S:0.002%, Cr:0.12%, Ni:0.71%, Mo:0.48%, V:0.01%, Cu:0.02%, Al:0.01%, Co:0.02%, As:0.002%, Sn:0.002%, Sb:0.0007%, B:0.0002%, H:0.8ppm, all the other compositions are Fe.
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN108728724A (en) * | 2018-06-05 | 2018-11-02 | 南京航空航天大学 | A method of improving ferritic steel anti-radiation performance by adding micro Au |
| CN112585699A (en) * | 2018-08-21 | 2021-03-30 | 住友电气工业株式会社 | Covered electric wire, electric wire with terminal, copper alloy wire, copper alloy stranded wire, and method for producing copper alloy wire |
| CN115233089A (en) * | 2022-05-16 | 2022-10-25 | 季华实验室 | Special steel for flexible gear and preparation process thereof |
| CN117226218A (en) * | 2023-09-22 | 2023-12-15 | 东方法马通核泵有限责任公司 | Build-up welding process of pressurized water reactor nuclear power coolant main pump |
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| CN102260835A (en) * | 2011-07-27 | 2011-11-30 | 杭州萧山江盛铸锻有限公司 | Nuclear power steel 18MnNiMo and its preparation method |
| CN102912222A (en) * | 2012-10-14 | 2013-02-06 | 浙江大隆合金钢有限公司 | 18MND5 low-alloy structural steel for nuclear power and technical control method for 18MND5 low-alloy structural steel |
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| CN102260835A (en) * | 2011-07-27 | 2011-11-30 | 杭州萧山江盛铸锻有限公司 | Nuclear power steel 18MnNiMo and its preparation method |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108728724A (en) * | 2018-06-05 | 2018-11-02 | 南京航空航天大学 | A method of improving ferritic steel anti-radiation performance by adding micro Au |
| CN108728724B (en) * | 2018-06-05 | 2020-04-21 | 南京航空航天大学 | Method for improving radiation resistance of ferritic steel by adding trace Au |
| CN112585699A (en) * | 2018-08-21 | 2021-03-30 | 住友电气工业株式会社 | Covered electric wire, electric wire with terminal, copper alloy wire, copper alloy stranded wire, and method for producing copper alloy wire |
| CN112585699B (en) * | 2018-08-21 | 2022-05-13 | 住友电气工业株式会社 | Covered electric wire, electric wire with terminal, copper alloy wire, copper alloy stranded wire, and method for producing copper alloy wire |
| CN115233089A (en) * | 2022-05-16 | 2022-10-25 | 季华实验室 | Special steel for flexible gear and preparation process thereof |
| CN117226218A (en) * | 2023-09-22 | 2023-12-15 | 东方法马通核泵有限责任公司 | Build-up welding process of pressurized water reactor nuclear power coolant main pump |
| CN117226218B (en) * | 2023-09-22 | 2024-04-23 | 东方法马通核泵有限责任公司 | Build-up welding process of pressurized water reactor nuclear power coolant main pump |
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