CN102157210B - Simplified assessment method for defects of welding joint area at piping safety end of pressure vessel of AP1000 nuclear reactor - Google Patents
Simplified assessment method for defects of welding joint area at piping safety end of pressure vessel of AP1000 nuclear reactor Download PDFInfo
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Abstract
The invention relates to a simplified assessment method for defects of a welding joint area at a piping safety end of a pressure vessel of an AP1000 nuclear reactor. The method comprises the following steps of: characterizing the detected dimension of a circumferential inner surface defect, and determining a defect depth a and a defect length l; calculating primary membrane stress sigma m which is vertical to a defect surface at the position of the circumferential inner surface defect in absence of the defect under an assessment working condition; calculating the relation of primary bending stress sigma b which is vertical to the defect surface at the position of the circumferential inner surface defect in absence of the defect and an extra bending moment M which is borne by the safety end through three-dimensional finite element analysis; determining the primary bending stress sigma b which corresponds to a resultant bending moment Mt according to the resultant bending moment Mt under the assessment working condition; calculating the rheological stress sigma f of a material in the welding joint area, and calculating a stress ratio SR which is equal to (sigma m+ sigma b)/ sigma f; calculating the relation of the stress ratio, a nominal defect length and a nominal permitted defect depth according to a three-dimensional finite element model; and judging whether the defect depth a is less than or equal to the permitted defect depth a or not.
Description
Technical field
The invention belongs to the Structure Integrity Assessment Technology field, be specifically related to be used for the simplification assessment method of the circumferential inner surface defective in AP1000 third generation adapter tube and safety end of nuclear reactor pressure vessel dissimilar metal welding line district.Be a kind ofly to be used to estimate and to differentiate before the labour of safe end weld metal zone and, be applicable to the safety management and the control of nuclear power generating equipment at the simplification assessment method of the security of circumferential excessive defect under the applying working condition condition of regulation of labour.
Background technology
Nuclear power is greatly developed in China as a kind of energy of clean and effective.Nuclear safety is the lifeline of nuclear power developing.Nuclear power industry is owing to its special reaction conditions and technological process, in case have an accident causing catastrophic consequence.The safe reliability that ensures nuclear power generating equipment is the major issue that countries in the world are paid close attention to always.
Operation reaches and is mainly pressurized water reactor type at the nuclear power station of building both at home and abroad at present, and the pressure vessel in the one of which loop links to each other with a primary loop piping through the connection tube safe end dissimilar metal welding joint.This pressure-bearing dissimilar metal welded stub connection is a kind of special welded structure, belongs to nuclear safety and pays close attention to the position.Because design and the requirement of using, this welding joint generally are on the low-alloy high-strength steel welding groove surface earlier in advance behind built-up welding one deck nickel-base alloy, with the nickel-base alloy wlding it and austenitic stainless steel are welded together again and obtain welding joint.Whole joint is made up of four kinds of materials, i.e. ferritic steel, nickel-base alloy overlay cladding, nickel-base alloy weld seam and austenitic stainless steel.Its design effort pressure is about 17MPa, and temperature is about 340 ℃.This joint manufacture difficulty is big; The welding of the dissimilar metal that it relates to is easy to generate weld defects; And complicated Thermal Cycle can cause low toughness material tissue and higher welding residual stress, in its use, is easy to generate defectives such as corrosion and fatigue crackle.Therefore; Dissimilar metal welding connector area becomes the weak link that possibly lose efficacy in a loop; The inefficacy of this key joints will cause the leakage of a loop radioactive water medium; Can cause the major accident of nuclear reactor pressure container dehydration and reactor core over hot melting, nuclear plant safety operation and environment are caused very big influence.Therefore, how accurately estimate with easy method and differentiate the safe end dissimilar metal weld metal zone make and using with in the security of the defective that produces, significant to the safe operation that ensures nuclear power generating equipment.
To the problem of nuclear power generating equipment defects assessment, developed multiple assessment method at present.ASME B&PV Code XI volume [ASME Boiler and Pressure Vessel Code like the U.S.; SectionXI; Rules for Construction of nuclear power plant components; 2007], the R6 of Britain [R6 Assessment of the integrity of structures containing defects, ProcedureR6-Revision 4.Gloucester:Nuclear Electric Ltd; 20011; RCC-MR A16 [Kayser Y, Marie S, the Poussard C of France; Delaval C.Leak Before Break procedure:Recent modification of RCC-MR A16 appendix and proposed improvements.International Journal of Pressure Vessels and Piping.2008,85:681-693] etc.In the existing in the world short-cut method that relates to the nuclear power generating equipment defects assessment; The adapter tube and safety end of nuclear reactor pressure vessel that generally will have complex geometry is reduced to straight tube and handles; The flaw size criterion that allows under certain operating loading that the method for the mechanical analysis that usefulness is approximate is set up; Estimate the security of defective, these methods are not accurately included the influence of safe end labyrinth geometry in.Welding joint generally also is reduced to mother metal and two kinds of materials of weld seam; Be positioned at the mother metal position different according to crackle with weld seam; Only get the mechanical property parameters of respective material and analyze, can't accurately handle the connection tube safe end dissimilar metal joint that constitutes by four kinds of materials (two kinds of weld seams and two kinds of mother metals).And existing method mainly is to setting up at the man-rate of the second generation nuclear power generating equipment defective of using as a servant, not necessarily being applicable to present structure and material at the advanced person's who builds third generation AP1000 nuclear power generating equipment.Through document and patent retrieval, both at home and abroad also not to the special method of nuclear power dissimilar metal welding joint defects assessment, more be not directed against the advanced third generation AP1000 nuclear power generating equipment or the special-purpose flaw evaluation method of parts at present.
Summary of the invention
Technical matters to be solved by this invention is to provide the simplification assessment method of the circumferential inner surface defective in a kind of AP1000 of being applicable to third generation adapter tube and safety end of nuclear reactor pressure vessel dissimilar metal welding line district.
The simplification assessment method of the circumferential inner surface defective of a kind of AP1000 adapter tube and safety end of nuclear reactor pressure vessel of the present invention weld metal zone comprises:
(1) detected circumferential inner surface defective is carried out characterization of size; The maximum distance that said defective is extended radially outwardly from circumferential inner surface is characterized by depth of defect a, and will be respectively be characterized by defect length l through said defective along the arc length between the two-end-point that circumferentially extends, when said circumferential inner surface extends radially outwardly to said maximum distance 2;
A membrane stress σ when (2) calculating circumferential inner surface defective locations place under the evaluation operating mode perpendicular to the zero defect of blemish surface through following formula
m,
σ
m＝pD/4t
In the formula:
P is the safe end pipe internal pressure under the evaluation operating mode,
D is the safe end external diameter of pipe,
T is the safe end thickness of pipe,
σ
mDimension be MPa;
Give its different elastic-plastic material parameter based on the actual 3-D geometric model of safe end with the different materials in butt welded seam district and carry out dimensional Finite Element, the primary bending stress σ when obtaining circumferential inner surface defective locations place perpendicular to the zero defect of blemish surface
bWith the relation that adds moment M that safe end bears, said primary bending stress σ
bDimension be MPa, the said dimension that adds moment M is KN.m;
According to said primary bending stress σ
bConfirm the corresponding primary bending stress σ of synthetic total moment M t under the said evaluation operating mode with the relation that adds moment M
b
Calculate the material flowing deformation stress σ of said weld metal zone through following formula
f,
σ
f＝(σ
y+σ
u)/2
In the formula:
σ
yAnd σ
uBe respectively the yield strength of material under working temperature and corresponding pulling strengrth of said weld metal zone, unit is MPa;
Through following formula calculated stress than SR:
SR＝(σ
m+σ
b)/σ
f；
(3) calculate the depth of defect a of permission of normalized defect length l/ π D and the normalized of stress ratio SR, circumferential inner surface defective according to three-dimensional finite element model
AllowThe relation of/t;
The said stress ratio SR that calculates according to step (2) and the normalized defect length l/ π D of said detected circumferential inner surface defective confirm the depth of defect a of the permission of normalized
Allow/ t;
(4), calculate the depth of defect a of permission according to said safe end thickness of pipe t
Allow
If the depth of defect a of said depth of defect a≤said permission
Allow, then said detected circumferential inner surface defective is safe under said evaluation operating mode.
Can differentiate the security of circumferential inner surface defective under the applying working condition condition of regulation of safe end dissimilar metal weld metal zone through the present invention, remedy to the special method of adapter tube and safety end of nuclear reactor pressure vessel dissimilar metal welding joint defects assessment and the disappearance that is directed against the special-purpose flaw evaluation method of advanced third generation AP1000 nuclear power generating equipment or parts.
Description of drawings
Fig. 1 is the characterization of size synoptic diagram according to the circumferential inner surface defective in AP1000 adapter tube and safety end of nuclear reactor pressure vessel dissimilar metal welding line of the present invention district.
Fig. 2 is the primary bending stress σ during perpendicular to the zero defect of blemish surface according to circumferential inner surface defective locations place, safe end of the present invention weld metal zone
bWith the change curve that adds moment M.
Fig. 3 allows degree of depth a according to safe end weld metal zone circumferential inner surface defective under the different stress ratio SR of the present invention
AllowThe relation curve family of the normalized defect length 1/ π D of/t and defective.
Embodiment
Below in conjunction with accompanying drawing the present invention is further specified.
The present invention is based on the advanced AP1000 third generation core voltage force container connection tube safe end dissimilar metal welded joint structure and the three-dimensional finite element model of material; The circumferential inner surface crackle that do not penetrate to different size in the Ni-based austenitic alloy weld seam of safe end has carried out detailed three-dimensional finite element limit load analysis calculating; Based on the ultimate load criterion of placticity failure, set up a kind of accurately special-purpose defective relevant and simplified assessment method with safe end structure, complicated joint material, crackle physical dimension and military service load.This method is used to differentiate the security of circumferential inner surface defective under the applying working condition condition of regulation of safe end dissimilar metal weld metal zone according to " closing in using " principle.Evaluation person only need be through characterizing the size of intending the evaluation defective, the stress of simple computation safe end; Can confirm the depth of defect that safe end allows through the mode of accompanying drawing or form interpolation; Through the degree of depth of plan evaluation defective and the comparison of the allowable defect degree of depth, can estimate the security of defective.Its concrete estimation steps comprises:
(1) defective characterizes:
The weld metal zone circumferential inner surface defective in the end of term in evaluation week of calculating with the circumferential inner surface excessive defect in detected AP1000 adapter tube and safety end of nuclear reactor pressure vessel dissimilar metal welding line district or by relevant criterion, standard; Be characterized by size shown in Figure 1, determine the depth of defect a and the defect length l of the defective of intending evaluation.As shown in Figure 1; The maximum distance that said defective is extended radially outwardly from circumferential inner surface is characterized by depth of defect a, and will be respectively be characterized by defect length l through said defective along the arc length between the two-end-point that circumferentially extends, when said circumferential inner surface extends radially outwardly to said maximum distance 2.
(2) confirming of safe end stress:
A membrane stress σ for safe end weld metal zone circumferential inner surface defective locations place during perpendicular to the zero defect of blemish surface
mPressing following formula (1) calculates:
σ
m＝pD/4t (1)
Wherein p is the pipe internal pressure of safe end under the evaluation operating mode, and D is the external diameter of pipe of safe end, and t is the thickness of pipe of safe end, σ
mDimension be MPa.
The primary bending stress σ of circumferential inner surface defective locations place, weld metal zone during perpendicular to the zero defect of blemish surface
bObtain through Fig. 2.Fig. 2 adds the primary bending stress σ under the moment M effect for the AP1000 safe end that three-dimensional finite element analysis calculates in difference
bIn this calculating, adopt the actual 3-D geometric model of connection tube safe end dissimilar metal welded joint structure, thereby effectively included the influence of safe end geometry in.Give its different elastic-plastic material parameter through butt joint Head Section different materials, included the influence of dissimilar metal material with complex in.Synthetic total moment M t that the load combinations that safe end bears under the different operating modes produces can obtain from design report, and its dimension is KN.m.σ
bAlso can calculate through the following formula (2) of Fig. 2 curve fitting, soon the M in the value substitution formula (2) of Mt calculates, wherein σ
bDimension be MPa, the dimension of M is KN.m.
σ
b＝58.87+0.017M+6.86×10
-7M
2-2.47×10
-11M
3 (2)
Wherein the span of M is 0-25000KN.m.
Calculate σ
mAnd σ
bAfter, by following formula (3) calculated stress than SR:
SR＝(σ
m+σ
b)/σ
f (3)
The flow stress σ of safe end weld metal zone material wherein
f=(σ
y+ σ
u)/2, σ
yBe the yield strength of safe end nickel-base alloy weld metal zone material under working temperature, σ
uBe corresponding pulling strengrth.σ
yAnd σ
uThe value that available experiment records or check in through relevant standard handbook.
(3) allowable defect determining dimensions:
For a membrane stress σ under different operating modes (nominal situation A, unusual service condition B, critical operating mode C and the accident conditions D) load
mWith primary bending stress σ
b, calculated stress compares SR.By the normalized defect length l/ π D of SR, confirm the depth of defect a of the permission of normalized with Fig. 3 interpolation with the defective of intending evaluation
Allow/ t; Or confirm the depth of defect a of the permission of normalized with table 1 interpolation that Fig. 3 makes
Allow/ t.For the situation of annotating (3) in the table 1, confirm the depth of defect a of the permission of normalized with table 2
Allow/ t.The depth of defect that calculates the minimum of confirming under the different operating loading promptly is the depth of defect a of acceptable permission
Allow
When evaluating, multiply by one greater than 1 safety coefficient k than SR, can obtain SR like counter stress with table 1
Peace Entirely=k*SR uses SR
SafetyCan determine the depth of defect a of conservative less permission through Fig. 3 or table 1
AllowSafety coefficient is analyzed definite by evaluation person according to the actual condition load condition voluntarily.
Depth of defect (a of the permission of the normalized of table 1 safe end weld metal zone circumferential inner surface defective
Allow/ t)
Annotate: (1) stress ratio: SR=(σ
m+ σ
b)/σ
f
(2) girth that obtains according to the external diameter of pipe D of safe end;
(3) acceptance criteria of use table 2
Table 2 is the depth of defect (a that annotate the permission of normalized under (3) situation in the table 1
Allow/ t)
Annotate: table 2 is tables of the ASME standard quoted, wherein:
A: depth of defect; L: defect length; a
Allow: the depth of defect of permission; T: safe end thickness of pipe.
(4) the defective security is passed judgment on:
When the depth of defect a of the defect in inner surface of intending evaluation less than depth of defect a corresponding to the permission of defect length l
AllowThe time, defective can be accepted, and safe end can continue to use under the applying working condition condition of regulation, and promptly depth of defect is accepted criterion and is: a≤a
AllowIf the criterion of accepting of this elementary simplification evaluation does not satisfy, can use senior Failure Assessment drawing method evaluation.
Embodiment 1
(1) defective characterizes:
As having detected the circumferential inner surface excessive defect in AP1000 safe end dissimilar metal weld metal zone or having calculated the flaw size of evaluating the end of term in week, characterize by Fig. 1 and determine depth of defect a=32mm and defect length 1=448mm.
(2) confirming of safe end stress:
The external diameter of pipe D=952.5mm of AP1000 adapter tube and safety end of nuclear reactor pressure vessel, thickness of pipe t=82.6mm gets the pipe internal pressure p=17MPa of design, then can calculate membrane stress one time by formula (1):
σ
m＝pD/4t＝49MPa。
The yield strength σ of safe end nickel-base alloy weld metal zone material under 340 ℃ of working temperatures that get of test strictly according to the facts
y=365MPa, pulling strengrth σ
u=635MPa then can calculate material flowing deformation stress:
σ
f＝(σ
y+σ
u)/2＝500MPa。
Synthetic total moment M t=10940KN.m that a load combinations of under operating mode B, bearing like acquisition safe end from design report produces then can calculate primary bending stress σ with the value substitution Fig. 2 of Mt or the M in the formula (2)
b=281MPa.
Calculate σ
m, σ
fAnd σ
bAfter, available formula (3) calculates stress ratio:
SR＝(σ
m+σ
b)/σ
f＝0.66.
(3) allowable defect determining dimensions:
By defect length 1=448mm, safe end external diameter of pipe D=952.5mm calculates normalized defect length l/ π D=0.15.Determine the depth of defect a of the permission of normalized with Fig. 3 or table 1 through stress ratio SR=0.66 and defect length 1/ π D=0.15
Allow/ t=0.78.By safe end thickness of pipe t=82.6mm, calculate the depth of defect a of permission
Allow=64.4mm.
(4) the defective security is passed judgment on:
The depth of defect a=32mm that is evaluated is less than the depth of defect a that allows
Allow=64.4mm, defective can be accepted, and promptly safe end can continue to use under the applying working condition condition of regulation.
, be about to further raising of operating loading and obtain SR than the safety coefficient that SR=0.66 multiply by k=1.25 like counter stress
Safety=k*SR=0.825 then can be determined the depth of defect a of the permission of normalized by table 1 interpolation
Fair Permitted/ t=0.55, the depth of defect a of permission
Allow=45.4mm.This result means under higher unusual service condition load, is still safe less than 45.4mm and length less than the defective of 448mm for the degree of depth.Safety coefficient is relevant with the operating loading of safe end in the design report, analyzes definite voluntarily by evaluation person.
Above embodiment only is used for explanation but does not limit the present invention.The present invention also has various deformation and improvement within the scope of the claims.Simple, the equivalence that every foundation claims of the present invention and description are done changes and modifies, and all falls into the claim protection domain of patent of the present invention.
Claims (5)
1. the simplification assessment method of the circumferential inner surface defective of an AP1000 adapter tube and safety end of nuclear reactor pressure vessel weld metal zone comprises:
(1) detected circumferential inner surface defective is carried out characterization of size; The maximum distance that said defective is extended radially outwardly from circumferential inner surface is characterized by depth of defect a, and will be respectively be characterized by defect length l through said defective along the arc length between the two-end-point that circumferentially extends, when said circumferential inner surface extends radially outwardly to said maximum distance 2;
A membrane stress σ when (2) calculating circumferential inner surface defective locations place under the evaluation operating mode perpendicular to the zero defect of blemish surface through following formula
m,
σ
m=pD/4t
In the formula:
P is the safe end pipe internal pressure under the evaluation operating mode,
D is the safe end external diameter of pipe,
T is the safe end thickness of pipe,
σ
mDimension be MPa;
Give its different elastic-plastic material parameter based on the actual 3-D geometric model of safe end with the different materials in butt welded seam district and carry out dimensional Finite Element, the primary bending stress σ when obtaining circumferential inner surface defective locations place perpendicular to the zero defect of blemish surface
bWith the relation that adds moment M that safe end bears, said primary bending stress σ
bDimension be MPa, the said dimension that adds moment M is KN.m;
Said primary bending stress σ
bCan confirm through following formula with the relation that adds moment M:
σ
b=58.87+0.017M+6.86×10
-7M
2-2.47×10
-11M
3
The span that adds moment M described in the formula is 0-25000KN.m;
According to said primary bending stress σ
bConfirm the corresponding primary bending stress σ of synthetic total moment M t under the said evaluation operating mode with the relation that adds moment M
b
Calculate the material flowing deformation stress σ of said weld metal zone through following formula
f,
σ
f＝（σ
y+σ
u）/2
In the formula:
σ
yAnd σ
uBe respectively the yield strength of material under working temperature and corresponding pulling strengrth of said weld metal zone, unit is MPa;
Through following formula calculated stress than SR:
SR=(σ
m+σ
b)/σ
f；
(3) calculate the depth of defect a of permission of normalized defect length l/ π D and the normalized of stress ratio SR, circumferential inner surface defective according to three-dimensional finite element model
AllowThe relation of/t;
The depth of defect a of the normalized defect length l/ π D of said stress ratio SR, circumferential inner surface defective and the permission of normalized
AllowThe relation of/t can be confirmed through following form 1 and form 2:
Form 1 is the depth of defect (a of the permission of normalized
Allow/ t):
Wherein:
Annotating (1) is stress ratio SR=(σ
m+ σ
b)/σ
f,
Annotate (2) girth for obtaining according to said safe end external diameter of pipe D,
Annotate (3) for using the acceptance criteria of form 2;
Form 2 is the depth of defect (a that annotates the permission of normalized under (3) situation in the table 1
Allow/ t):
The said stress ratio SR that calculates according to step (2) and the normalized defect length l/ π D of said detected circumferential inner surface defective confirm the depth of defect a of the permission of normalized
Allow/ t;
(4), calculate the depth of defect a of permission according to said safe end thickness of pipe t
Allow
If the depth of defect a of said depth of defect a≤said permission
Allow, then said detected circumferential inner surface defective is safe under said evaluation operating mode.
2. method according to claim 1 is characterized in that, also is included in the said step (2) the said stress ratio SR that calculates multiply by one greater than 1 safety coefficient k, obtains SR
Safety=k*SR, thus in said step (3), determine the depth of defect a of the permission of conservative normalized
Allow/ t.
3. method according to claim 1 is characterized in that, the said synthetic total moment M t under the said evaluation operating mode in the said step (2) obtains from design report.
4. method according to claim 3 is characterized in that, the said evaluation operating mode in the said step (2) comprises nominal situation, unusual service condition, critical operating mode and accident conditions.
5. method according to claim 1 is characterized in that, the said yield strength σ in the said step (2)
yWith said pulling strengrth σ
uRecord or check in through experiment through the standard handbook.
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| CN102157211B (en) * | 2010-12-09 | 2013-01-16 | 华东理工大学 | Assessment method for defects of welding joint area at piping safety end of pressure vessel of AP1000 nuclear reactor |
| CN102494940B (en) * | 2011-12-13 | 2013-05-08 | 华东理工大学 | Calibration method for brittle fracture evaluation parameters of materials based on Beremin model |
| CN103366841B (en) * | 2013-08-06 | 2015-12-09 | 苏州热工研究院有限公司 | The assessment method of a kind of CPR1000 unit reactor pressure vessel reactor core cylinder district defect |
| CN103868985B (en) * | 2014-03-20 | 2017-01-18 | 西南石油大学 | Defect quantified comprehensive safety judgment method for on-service pressure container |
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