CN102157210A - 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 PDF

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CN102157210A
CN102157210A CN2010105812303A CN201010581230A CN102157210A CN 102157210 A CN102157210 A CN 102157210A CN 2010105812303 A CN2010105812303 A CN 2010105812303A CN 201010581230 A CN201010581230 A CN 201010581230A CN 102157210 A CN102157210 A CN 102157210A
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defect
depth
circumferential inner
stress
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CN102157210B (en
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王国珍
刘志伟
轩福贞
涂善东
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East China University of Science and Technology
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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

AP1000 adapter tube and safety end of nuclear reactor pressure vessel weld metal zone defective is simplified assessment method
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 because its special reaction conditions and technological process will cause catastrophic consequence in case have an accident.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 loop links to each other with a primary loop piping by 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 behind earlier pre-built-up welding one deck nickel-base alloy on the low-alloy high-strength steel welding groove surface, with the nickel-base alloy wlding it and austenitic stainless steel are welded together again and obtain welding joint.Whole joint is made 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, is easy to generate defectives such as corrosion and fatigue crackle in its use.Therefore, dissimilar metal welding connector area becomes the weak link that may 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.
At the problem of nuclear power generating equipment defects assessment, developed multiple assessment method at present.ASME B﹠amp as the U.S.; PV Code XI rolls up [ASME Boiler and Pressure Vessel Code, SectionXI, Rules for Construction of nuclear power plant components, 2007], the R6[R6 Assessment of the integrity of structures containing defects of Britain, ProcedureR6-Revision 4.Gloucester:Nuclear Electric Ltd, 20011, the RCC-MR A16[Kayser Y of France, Marie S, Poussard C, 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 of setting up with the method for approximate mechanical analysis, 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 at 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 at the special method of nuclear power dissimilar metal welding joint defects assessment, more there is not special-purpose flaw evaluation method at present at advanced person's third generation AP1000 nuclear power generating equipment or parts.
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 described 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 described defective along the arc length between the two-end-point that circumferentially extends, when described circumferential inner surface extends radially outwardly to described 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 by 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, described primary bending stress σ bDimension be MPa, the described dimension that adds moment M is KN.m;
According to described primary bending stress σ bDetermine the corresponding primary bending stress σ of synthetic total moment M t under the described evaluation operating mode with the relation that adds moment M b
Calculate the material flowing deformation stress σ of described weld metal zone by following formula f,
σ f=(σ yu)/2
In the formula:
σ yAnd σ uBe respectively the yield strength of material under working temperature and the corresponding pulling strengrth of described weld metal zone, unit is MPa;
By following formula calculated stress than SR:
SR=(σ mb)/σ f
(3) calculate the depth of defect a of the permission of the nominal defect length l/ π D of stress ratio SR, circumferential inner surface defective and nominalization according to three-dimensional finite element model AllowThe relation of/t;
The described stress ratio SR that calculates according to step (2) and the nominal defect length l/ π D of described detected circumferential inner surface defective determine the depth of defect a of the permission of nominalization Allow/ t;
(4), calculate the depth of defect a of permission according to described safe end thickness of pipe t Allow
If the depth of defect a of described depth of defect a≤described permission Allow, then described detected circumferential inner surface defective is safe under described evaluation operating mode.
The security of the circumferential inner surface defective that can differentiate the safe end dissimilar metal weld metal zone by the present invention under the applying working condition condition of regulation remedied at the special method of adapter tube and safety end of nuclear reactor pressure vessel dissimilar metal welding joint defects assessment and at the disappearance of the special-purpose flaw evaluation method of advanced person's 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 nominal defect length 1/ π D of/t and defective.
Embodiment
The present invention is further described below in conjunction with accompanying drawing.
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 by characterizing the size of intending the evaluation defective, the stress of simple computation safe end, can determine the depth of defect that safe end allows by the mode of accompanying drawing or form interpolation, by intending evaluating the degree of depth of 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 described 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 described defective along the arc length between the two-end-point that circumferentially extends, when described circumferential inner surface extends radially outwardly to described maximum distance 2.
(2) determining 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 by Fig. 2.The AP1000 safe end that Fig. 2 calculates for three-dimensional finite element analysis adds primary bending stress σ under the moment M effect 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 by 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 by 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 mb)/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 by 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 nominal defect length l/ π D of SR, determine the depth of defect a of the permission of nominalization with Fig. 3 interpolation with the defective of intending evaluation Allow/ t; Or determine the depth of defect a of the permission of nominalization with table 1 interpolation that Fig. 3 makes Allow/ t.For the situation of annotating (3) in the table 1, determine the depth of defect a of the permission of nominalization with table 2 Allow/ t.The depth of defect that calculates the minimum of determining 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 as counter stress with table 1 Peace Entirely=k*SR uses SR SafetyCan determine the depth of defect a of conservative less permission by 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 nominalization 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 nominalization under (3) situation in the table 1 Allow/ t)
Figure BDA0000037175100000062
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 evaluate with senior Failure Assessment drawing method.
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) determining 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 yu)/2=500MPa。
Synthetic total moment M t=10940KN.m that a load combinations of bearing under operating mode B as 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 mb)/σ f=0.66.
(3) allowable defect determining dimensions:
By defect length 1=448mm, safe end external diameter of pipe D=952.5mm calculates nominal defect length l/ π D=0.15.Determine the depth of defect a of the permission of nominalization with Fig. 3 or table 1 by 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:
Assessed depth of defect a=32mm 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 as counter stress Safety=k*SR=0.825 then can be determined the depth of defect a of the permission of nominalization 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 (7)

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 described 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 described defective along the arc length between the two-end-point that circumferentially extends, when described circumferential inner surface extends radially outwardly to described 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 by 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, described primary bending stress σ bDimension be MPa, the described dimension that adds moment M is KN.m;
According to described primary bending stress σ bDetermine the corresponding primary bending stress σ of synthetic total moment M t under the described evaluation operating mode with the relation that adds moment M b
Calculate the material flowing deformation stress σ of described weld metal zone by following formula f,
σ f=(σ yu)/2
In the formula:
σ yAnd σ uBe respectively the yield strength of material under working temperature and the corresponding pulling strengrth of described weld metal zone, unit is MPa;
By following formula calculated stress than SR:
SR=(σ mb)/σ f
(3) calculate the depth of defect a of the permission of the nominal defect length l/ π D of stress ratio SR, circumferential inner surface defective and nominalization according to three-dimensional finite element model AllowThe relation of/t;
The described stress ratio SR that calculates according to step (2) and the nominal defect length l/ π D of described detected circumferential inner surface defective determine the depth of defect a of the permission of nominalization Allow/ t;
(4), calculate the depth of defect a of permission according to described safe end thickness of pipe t Allow
If the depth of defect a of described depth of defect a≤described permission Allow, then described detected circumferential inner surface defective is safe under described evaluation operating mode.
2. method according to claim 1 is characterized in that, the described primary bending stress σ in the described step (2) bCan determine by 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.
3. method according to claim 1 is characterized in that, the depth of defect a of the nominal defect length l/ π D of the described stress ratio SR in the described step (3), circumferential inner surface defective and the permission of nominalization AllowThe relation of/t can be determined by following form 1 and form 2:
Form 1 is the depth of defect (a of the permission of nominalization Allow/ t):
Figure FDA0000037175090000021
Wherein:
Annotating (1) is stress ratio SR=(σ m+ σ b)/σ f,
Annotate (2) girth for obtaining according to described 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 nominalization under (3) situation in the table 1 Allow/ t):
Figure FDA0000037175090000031
4. method according to claim 1 is characterized in that, also is included in the described step (2) the described stress ratio SR that calculates be multiply by one greater than 1 safety coefficient k, obtains SR Safety=k*SR, thus in described step (3), determine the depth of defect a of the permission of conservative nominalization Allow/ t.
5. method according to claim 1 is characterized in that, the described synthetic total moment M t under the described evaluation operating mode in the described step (2) obtains from design report.
6. method according to claim 5 is characterized in that, the described evaluation operating mode in the described step (2) comprises nominal situation, unusual service condition, critical operating mode and accident conditions.
7. method according to claim 1 is characterized in that, the described yield strength σ in the described step (2) yWith described pulling strengrth σ uRecord by experiment or check in by the standard handbook.
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CN102157211A (en) * 2010-12-09 2011-08-17 华东理工大学 High-level assessment method for defects of welding joint area at piping safety end of pressure vessel of AP1000 nuclear reactor
CN102494940A (en) * 2011-12-13 2012-06-13 华东理工大学 Calibration method for brittle fracture evaluation parameters of materials based on Beremin model
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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102157211A (en) * 2010-12-09 2011-08-17 华东理工大学 High-level assessment method for defects of welding joint area at piping safety end of pressure vessel of AP1000 nuclear reactor
CN102494940A (en) * 2011-12-13 2012-06-13 华东理工大学 Calibration method for brittle fracture evaluation parameters of materials based on Beremin model
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
CN103366841A (en) * 2013-08-06 2013-10-23 苏州热工研究院有限公司 Evaluation method for defects of CPR1000 unit reactor pressure vessel core cylindrical shell zones
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
CN103868985A (en) * 2014-03-20 2014-06-18 西南石油大学 Defect quantified comprehensive safety judgment method for on-service pressure container
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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