WO2011078333A1 - 原子力発電プラントの健全性評価システム - Google Patents
原子力発電プラントの健全性評価システム Download PDFInfo
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- WO2011078333A1 WO2011078333A1 PCT/JP2010/073364 JP2010073364W WO2011078333A1 WO 2011078333 A1 WO2011078333 A1 WO 2011078333A1 JP 2010073364 W JP2010073364 W JP 2010073364W WO 2011078333 A1 WO2011078333 A1 WO 2011078333A1
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- crack
- stress distribution
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N17/00—Investigating resistance of materials to the weather, to corrosion, or to light
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
- G01M5/00—Investigating the elasticity of structures, e.g. deflection of bridges or air-craft wings
- G01M5/0033—Investigating the elasticity of structures, e.g. deflection of bridges or air-craft wings by determining damage, crack or wear
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the present invention relates to soundness evaluation in a nuclear power plant.
- stress corrosion cracking (SCC) of metal materials used in structures and piping has become a problem in nuclear power plants.
- SCC stress corrosion cracking
- the stress corrosion cracking is a fracture phenomenon that occurs when corrosion and tensile stress are simultaneously applied to a metal material. If the stress is large, the phenomenon may be manifested in a shorter period of time.
- Patent Document 1 a method for evaluating stress corrosion cracking based on the hardness of a structural material is known (for example, see Patent Document 1). This method focuses on the fact that there is a correlation between the hardness of the structural material and the magnitude of stress corrosion cracking, and evaluates the sensitivity and life of stress corrosion cracking of the structural material using this correlation.
- the conventional technique for evaluating the sensitivity of stress corrosion cracking based on the hardness as described above can only evaluate stress corrosion cracking near the surface of the structural material, for example, about several millimeters from the surface to the inside. There was an inconvenience that the above corrosion cracks could not be evaluated.
- the degree of progress of stress corrosion cracking varies depending on the environment used (temperature, pressure, etc.), but the conventional technology for judging cracks from the hardness of the structural material described above is an evaluation that takes into account the environment used. There was a problem that it was difficult to do.
- the present invention has been made in view of such circumstances, and while improving the accuracy of soundness evaluation, the soundness of a nuclear power plant that can provide appropriate maintenance measures based on the evaluation results
- the purpose is to provide an evaluation system.
- the present invention is a soundness evaluation system in a nuclear power plant, and calculates a stress distribution of residual stress of a soundness evaluation structure, and determines that a crack is generated based on the stress distribution.
- a stress distribution calculation unit that outputs the distribution and the specified crack generation point, and the crack propagation from the crack generation point based on the stress distribution output from the stress distribution calculation unit and the information on the specified crack generation point
- a crack growth prediction unit that performs prediction and outputs the prediction result, and a database that associates the crack growth prediction result with maintenance measures, and corresponds to the crack growth prediction result from the crack growth prediction unit
- a nuclear power plant soundness evaluation system including a maintenance measure that reads maintenance measures to be read from the database and presents the read maintenance information to a user.
- the stress distribution calculation unit calculates the stress distribution of the residual stress of the evaluation structure, and determines whether or not a crack is generated based on the stress distribution, and determines that the crack is generated
- the crack propagation prediction unit performs crack propagation prediction based on the stress distribution.
- the stress distribution calculation unit calculates the continuous residual stress distribution from the inner surface to the surface of the evaluation structure in consideration of the environment in which the evaluation structure is used.
- the stress distribution calculation unit performs an elastic analysis in advance on each structure when a plurality of the same structures exist, and groups the results of the elastic analysis approximated.
- To create a plurality of groups to obtain a stress distribution by performing an elastoplastic analysis of the structure in each of the groups, and has a database that stores the group and the stress distribution in association with each other,
- the stress distribution of the residual stress of the soundness evaluation structure may be acquired from the database.
- the elastic analysis is performed on a plurality of structures, and the structures showing the elastic analysis results to be approximated are grouped, and the elasto-plastic analysis is performed on each group in advance to obtain the stress distribution.
- the time of distribution calculation it is only necessary to acquire information from the database, so that the stress distribution can be acquired easily and in a short time.
- the stress distribution calculation unit may obtain the stress distribution of the residual stress by regarding the residual stress of the soundness evaluation structure as a yield stress.
- FIG. 1 a soundness evaluation system for a nuclear power plant according to a first embodiment of the present invention
- FIG. 2 a case where the soundness of the primary coolant pipe 3 of the reactor vessel 2 in the nuclear power plant 1 is evaluated as illustrated in FIG. 1 will be described as an example. More specifically, as shown in FIG. 2, the case where the soundness of the butt weld portion 4 in the primary coolant pipe 3 is evaluated will be described as an example.
- FIG. 1 the high-temperature high-pressure water 5 sent from the reactor vessel 2 flows into the steam generator 6 through the primary coolant pipe 3.
- FIG. 3 is a diagram showing a schematic configuration of the soundness evaluation system 10 according to the present embodiment.
- the soundness evaluation system 10 includes a stress distribution calculation unit 11, a crack growth prediction unit 12, a soundness maintenance unit 13, a stress distribution database 14, and a maintenance database 15. As prepared.
- the stress distribution calculation unit 11 performs mesh division for residual stress analysis as shown in FIGS. 4A and 4B, and uses this mesh division to calculate the residual stress by thermoelastic-plastic analysis.
- FIG. 5 shows a mesh division example (solid line in the figure) for actual residual stress analysis in the butt weld 4 in the primary coolant pipe 3 shown in FIG. 2, and the residual calculated using this mesh division.
- An example of stress distribution (dotted line in the figure) is shown.
- information required for calculating the residual stress for example, the size of the evaluation structure, material (including physical properties), welding conditions, installation environment, etc. It is input and registered by.
- the stress distribution calculation unit 11 has a stress distribution database 14 in which a threshold stress distribution when a crack occurs is stored for each structure and for each analysis position of the structure.
- the threshold stress distribution stored in the stress distribution database 14 is created by performing a test in advance.
- the stress distribution calculation unit 11 reads the threshold stress distribution corresponding to the current evaluation structure from the stress distribution database 14, compares the read threshold stress distribution with the residual stress distribution obtained by calculation, and the residual stress is the threshold stress. It is determined whether or not there is a part that exceeds. As a result, if the residual stress is equal to or less than the threshold stress in the entire evaluation region, it is determined that no maintenance measure is required in the current evaluation, and the current calculation result is stored in a predetermined database (not shown).
- the crack propagation prediction unit 12 sets the shape of the leading edge (tip) of the initial crack at the crack occurrence location specified by the stress distribution calculation unit 11, and performs subdivision of the mesh. For example, the mesh is subdivided according to the shape of the leading edge of the initial crack so that the node of the mesh is positioned on the leading edge of the initial crack. Subsequently, the residual stress calculated by the stress distribution calculation unit 11 is set on the subdivided mesh.
- the initial crack is positioned so that the mesh node 14A is positioned on the leading edge 13A of the initial crack.
- the mesh is subdivided according to the shape of the leading edge 13A.
- the initial crack portion that is, the node 14B in front (inner side) of the front edge 13A of the initial crack can be released later to propagate the crack (simulate the initial crack).
- the residual stress calculated by the stress distribution calculation unit 11 is set on the subdivided mesh.
- FIG. 6 shows an actual mesh division example (solid line) by this mesh subdivision and an example of an initial residual stress distribution (dotted line) set on this mesh division.
- the crack propagation prediction unit 12 calculates the residual stress when the initial crack is introduced by releasing the initial crack, that is, the node before the leading edge of the initial crack.
- a fracture mechanics parameter K stress intensity factor
- K stress intensity factor
- FIGS. 4 (e) and 4 (f) the node 14B before the leading edge 13A of the initial crack is released.
- the released node 14B is indicated by a white circle, and the mesh of the release portion is indicated by a dotted line.
- the residual stress when the initial crack is introduced is calculated, and the fracture mechanics parameter K is obtained based on this residual stress.
- This fracture mechanics parameter is determined at each node on the crack leading edge.
- FIG. 7 shows an actual mesh division example (solid line) at this time and an example of the residual stress distribution calculated based on the mesh division (dotted line).
- the crack propagation predicting unit 12 obtains the residual stress distribution and the fracture mechanics parameter K in this manner, the crack propagation direction and the amount of progress are determined from a predetermined crack propagation law based on these information. Predict.
- the crack propagation law is well known, and is expressed, for example, by the following equation (1).
- FIGS. 8A and 8B illustrate the predicted crack propagation. As shown in FIGS. 8A and 8B, for example, the entire edge 13B of the crack after prediction is represented by a one-dot chain line. Note that the mesh division shown in FIGS. 8A and 8B is the same as the mesh division shown in FIGS. 4E and 4F.
- the crack propagation prediction unit 12 recreates the mesh in accordance with the predicted crack leading edge shape so that the node of the mesh is positioned on the predicted crack leading edge.
- the crack propagation prediction unit 12 recreates the mesh in accordance with the predicted crack leading edge shape so that the node of the mesh is positioned on the predicted crack leading edge.
- the nodes on the front (inner side) of the crack leading edge after prediction that is, the nodes on the crack leading edge before prediction and between the crack leading edge before prediction and the crack leading edge after prediction are Set it so that it can be released later to propagate the crack.
- the mesh is recreated so that the number of mesh divisions between the crack leading edge 13A before prediction and the crack leading edge 13B after prediction is equal. No, it can be divided by any mesh shape, and the number of divisions does not need to be equal.
- the amount of information such as stress and strain in the previous mesh is set.
- state quantities such as stress and strain of the previous mesh as shown in FIGS. 8A and 8B are set on a new mesh as shown in FIGS. 8C and 8D.
- the node before the predicted crack leading edge that is, the node on the crack leading edge before the prediction or the node between the crack leading edge before the prediction and the crack leading edge after the prediction is released.
- the crack growth is simulated.
- the node before the predicted crack leading edge is released in this way.
- the crack can propagate to the leading edge of the crack.
- the stress at the front portion of the predicted crack leading edge is released, and the stress at the predicted leading edge portion of the crack is maximized.
- a fracture mechanics parameter K is obtained for the crack shape after the progress.
- the fracture mechanics parameter K is obtained, for example, at each node on the crack leading edge.
- the crack propagation is simulated by releasing the node 14A on the leading edge 13A of the crack before prediction.
- the released node 14A is indicated by a white circle, and the mesh of the release portion is indicated by a dotted line.
- the fracture mechanics parameter K on the new mesh is obtained in this way, the crack propagation direction and amount are predicted based on the fracture mechanics parameter K. Then, the cracks are sequentially propagated by repeatedly performing the above-described processing.
- FIG. 10 shows an actual mesh division example (solid line) and a stress distribution example (dotted line) when a crack propagates to half the plate thickness t of the pipe.
- FIGS. 5 to 7 show examples of mesh division in the case of analyzing the progress of a crack generated on the inner peripheral surface side of the butt weld
- FIG. 10 shows the outer peripheral side of the butt weld 4.
- 3 shows an example of mesh division when analyzing the growth of a crack generated in Fig. 1. In FIG. 10, only the right half mesh division of the butt weld portion 4 is shown, and the left half is not shown.
- K is used as the fracture mechanics parameter, but other parameters (for example, J) may be used instead.
- a crack growth prediction method using another parameter J is disclosed in, for example, Japanese Patent Laid-Open No. 10-38829, and this method may be used to obtain a crack growth prediction result.
- the present invention is not limited to these methods, and any method may be used as long as it is a method for predicting crack propagation based on the stress distribution.
- the soundness maintenance unit 13 has a maintenance database 15 in which a crack growth threshold value and a maintenance pattern are stored in association with each other.
- the crack growth threshold is a threshold for crack growth at which it can be determined that the soundness of the target device can be maintained even though the crack has progressed after a predetermined period (for example, five years later). It is a value that can be set by performing
- the integrity maintenance unit 13 selects the following maintenance pattern A when the crack growth prediction result after a predetermined period is equal to or less than the crack growth threshold by the crack growth prediction unit 12, and sets the crack growth threshold to If it exceeds, the following maintenance pattern B is selected.
- Maintenance pattern A The operation is continued, and the following maintenance measures ( ⁇ ) to ( ⁇ ) are carried out at the next inspection.
- Maintenance pattern B Immediately implement the following maintenance measures ( ⁇ ) or ( ⁇ ).
- ( ⁇ ) Replacement A structure including a portion having a high residual stress and where cracks may be generated or propagated is replaced with an alternative structure with a reduced residual stress. This method is carried out when it is determined that it is structurally difficult to carry out the repair construction ( ⁇ ) above or that it is desirable to replace the structure as a result of the life evaluation of the target device.
- the integrity maintenance unit 13 has a repair technique for the maintenance target part. If the maintenance method can be handled at a lower cost and in a shorter time than other maintenance methods, a maintenance measure ( ⁇ ), And if repair parts are difficult or repair technology has not been built and replacement with an alternative structure can be handled at lower cost and in a shorter time than other maintenance methods, maintenance measures ( ⁇ ) Select. Maintenance measures ( ⁇ ) and ( ⁇ ) often require remodeling of the target equipment and are often extensive. Therefore, a maintenance measure ( ⁇ ) is selected to remove not only crack propagation but also stress, which is a factor of crack initiation, from the structure while utilizing existing equipment.
- the soundness maintenance unit 13 has a repair technique for the relevant maintenance unit. If the maintenance method can be handled at a lower cost and in a shorter time than other maintenance methods, a maintenance measure is provided. If ( ⁇ ) is selected and the part or repair technology that is difficult to repair is not constructed and replacement with an alternative structure can be handled at a lower cost and in a shorter time than other maintenance methods ( ⁇ ) Select.
- the health maintenance unit 13 is preliminarily input by the user with information on the relevant maintenance unit sufficient to select the above ( ⁇ ) to ( ⁇ ) for both of the maintenance patterns A and B. .
- the soundness maintenance unit 13 determines that the crack does not progress and the soundness of the target device can be maintained even if the crack propagation prediction unit 12 continues operation for a predetermined period (for example, 5 years). Determines that no maintenance measures are required.
- the soundness maintenance unit 13 selects either the maintenance pattern A or B or the maintenance measure unnecessary based on the crack growth prediction result input from the crack growth prediction unit 12, and in the case of the maintenance pattern A or B When a further appropriate maintenance measure is selected, the selected maintenance pattern and, if necessary, the maintenance measure are displayed on the display device.
- the worker refers to the maintenance measure displayed on the display device and executes this maintenance measure.
- the soundness maintenance unit 13 displays the maintenance pattern and maintenance measures ( ⁇ ) to ( ⁇ ) selected based on the crack growth prediction result input from the crack growth prediction unit 12 on the display device, thereby maintaining the maintenance measure. It is good also as making a user choose an appropriate thing about.
- FIG. 11 is a schematic view of the state in which the in-core instrument tube is supported by the lower mirror when viewed from the bottom of the in-furnace container, and FIG. 12 shows the state in which the in-core instrument tube is welded to the bottom of the furnace.
- a plurality of in-core instrumentation tubes 54 for passing sensors through are supported on the lower mirror of the reactor vessel.
- the in-core instrumentation tube 54 penetrates the furnace bottom 56, and the contact surface between the furnace bottom 56 and the in-core instrumentation tube 54 is welded so that each in-core instrumentation tube 54 is welded.
- the mounting cylinder 54 is fixed to the furnace bottom 56.
- the furnace bottom 56 has a bowl shape, and the stress distribution varies depending on the mounting angle between the in-core instrument tube 54 and the furnace bottom 56. Therefore, obtaining the stress distribution for each weld requires a great deal of labor and time.
- This embodiment provides a soundness evaluation system that can easily and quickly obtain the stress distribution for each of these structures even if the stress distribution has a complicated shape that varies depending on the location. To do.
- description is abbreviate
- the soundness evaluation system differs in the function of the stress distribution calculation unit according to the first embodiment shown in FIG. That is, in the first embodiment, the elasto-plastic analysis was performed for the target part of the soundness evaluation and the residual stress was calculated each time. However, in the present embodiment, the elasto-plastic analysis was performed in advance. The result is stored as a database.
- the results of the elastic analysis are compared, and the in-core instrument tubes that approximate the elastic analysis results are grouped.
- five groups I to V are created.
- one representative in-core instrumentation cylinder is defined for each group I to V
- an elasto-plastic analysis is performed on the in-core instrumentation cylinder
- a stress distribution is calculated, and this stress distribution data is associated with each group. And store it in the database.
- the stress distribution of the group to which the in-core instrumentation cylinder to be evaluated belongs is obtained from the database, and the soundness evaluation is performed using this stress distribution.
- the elastic analysis is performed for a plurality of parts, the parts showing the elastic analysis results to be approximated are grouped, and the elasto-plastic analysis is performed on each group in advance to obtain the stress distribution. Therefore, it is only necessary to acquire information from the database when calculating the actual stress distribution. Thereby, a stress distribution can be acquired easily and in a short time.
- the in-furnace instrumentation cylinder 54 has been described as an example, but the part for creating the database is not limited to this part.
- the present invention can be applied when there are a plurality of similar structures and their stress distributions differ depending on the region.
- the stress distribution may not be calculated in detail in the calculation of the stress distribution.
- the stress value of the weld metal portion may be regarded as equivalent to the yield stress and evaluated without calculating the stress distribution.
- the residual stress in the welded portion is equivalent to the yield stress in the upper portion of the welded portion, but the stress is reduced in the lower portion.
- crack growth is evaluated by regarding these as overall yield stress.
- the yield stress is obtained from the physical property value of the evaluation structure.
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Abstract
Description
また、応力腐食割れの進展度合いは、使用される環境(温度、圧力等)によって変化するが、上述した構造材の硬度からき裂を判定する従来の技術では、使用される環境等を考慮した評価を行うことが難しいといった問題があった。
しかしながら、近年、プラントの運転効率等を考慮して、き裂が確認された場合であっても、プラントの健全性が確保できる期間であれば、き裂をそのままにした状態で継続運転を行わせるといった新たな規格が構築されている。このような規格を適用する場合には、き裂の進展予測を可能な限り高い精度で行い、このき裂進展予測結果に応じて適切な時期に、適切な保全対策を実施することが必要となる。
本発明は、原子力発電プラントにおける健全性評価システムであって、健全性の評価構造体の残留応力の応力分布を算出し、該応力分布に基づいてき裂が発生すると判断した場合に、算出した応力分布および特定したき裂発生箇所を出力する応力分布算出部と、応力分布算出部から出力された応力分布および特定したき裂発生箇所の情報に基づいて、該き裂発生箇所からのき裂進展予測を行い、予測結果を出力するき裂進展予測部と、き裂進展予測結果と保全対策とが対応付けられたデータベースを有し、前記き裂進展予測部からのき裂進展予測結果に対応する保全対策を前記データベースから読み出し、読み出した保全情報をユーザに提示する健全性保全部とを備える原子力発電プラントの健全性評価システムを提供する。
以下に、本発明の第1実施形態に係る原子力発電プラントの健全性評価システム(以下、単に「健全性評価システム」という。)について、図面を参照して説明する。本実施形態では、図1に示すような、原子力発電プラント1における原子炉容器2の1次冷却材管3の健全性について評価する場合を例示して説明する。より具体的には、図2に示すように、1次冷却材管3における突合せ溶接部4の健全性を評価する場合を例示して説明する。なお、図1において、原子炉容器2から送出された高温高圧水5は、この1次冷却材管3を通って蒸気発生器6に流入するようになっている。
なお、上記残留応力の算出に必要となる情報(例えば、評価構造物のサイズ、材料(物性値含む)、溶接条件、設置環境等)については、応力分布の算出処理に先駆けて、予め作業員によって入力され、登録されているものとする。
また、予測後のき裂前縁の手前(内側)の節点、即ち、予測前のき裂前縁上の節点や予測前のき裂前縁と予測後のき裂前縁の間の節点は、後で解放してき裂を進展させることができるように設定する。なお、図9に示す例では、予測前のき裂前縁13Aと予測後のき裂前縁13Bとの間のメッシュ分割数が等しくなるようにメッシュを再作成しているが、必ずしもその必要はなく、任意のメッシュ形状で分割でき、分割数を等しくする必要はない。
保全パターンB:ただちに以下の(α)か(β)の保全対策を実施する。
(α)補修
残留応力が高く、き裂が発生、進展する可能性がある箇所を機械加工等にて削除し、耐食性を有する溶接材料等で盛りなおす。この方法は、トラブル対応時及び補修の必要性が高く、補修施工条件が比較的容易な場合に採用される場合が多い。
残留応力が高く、き裂が発生、進展する可能性がある箇所を含む構造物を、残留応力が低減された代替構造物にそのまま取り替える。この方法は、上記(α)の補修施工が構造的に難しい、または、対象機器の寿命評価を行った結果、構造物を取り替える方が望ましいと判断した場合に実施される。
残留応力が高く、き裂が発生、進展する可能性がある箇所に対して、応力を低減させる。
次に、本発明の第2実施形態に係る原子力発電プラントの健全性評価システムについて、図面を参照して説明する。
例えば、上述した第1実施形態において例示した突合せ溶接部4であれば、形状もそれほど複雑ではないために、残留応力分布の算出処理はそれほど煩雑ではないが、原子力発電プラントでは、複雑な形状の部位も多く、それらの部位において毎回残留応力分布を求めることは大変な労力と時間がかかる。例えば、炉内計装筒がその例である。図11は炉内計装筒が下部鏡に支持されている状態を炉内容器下側から見たときの模式図、図12は炉内計装筒が炉底に溶接されている状態を示した概略断面図である。
以下、本実施形態に係る原子力発電プラントの健全性評価システムについて、上述した第1実施形態に係る健全性評価システムと共通する点については説明を省略し、異なる点について主に説明する。
まず、図11及び図12に示した各炉内計装筒54について接合部に熱(所定の歪み)を仮想的に与え、そのときの感度解析(弾性解析)を行い、熱が与えられたときに発生する応力を評価する。この弾性解析は、塑性変形を考慮しないため、簡便にかつ短時間で行える。
そして、各グループIからVについて代表の炉内計装筒を一つ定め、その炉内計装筒において弾塑性解析を実施し、応力分布を算出し、この応力分布のデータを各グループと対応付けてデータベースに格納しておく。
そして、実際の残留応力の算出時においては、データベースから評価対象である炉内計装筒が属するグループの応力分布を取得し、この応力分布を用いて健全性評価を行う。
11 応力分布算出部
12 き裂進展予測部
13 健全性保全部
14 応力分布データベース
15 保全データベース
Claims (3)
- 健全性の評価構造体の残留応力の応力分布を算出し、該応力分布に基づいてき裂が発生すると判断した場合に、算出した応力分布および特定したき裂発生箇所を出力する応力分布算出部と、
応力分布算出部から出力された応力分布および特定したき裂発生箇所の情報に基づいて、該き裂発生箇所からのき裂進展予測を行い、予測結果を出力するき裂進展予測部と、
き裂進展予測結果と保全対策とが対応付けられたデータベースを有し、前記き裂進展予測部からのき裂進展予測結果に対応する保全対策を前記データベースから読み出し、読み出した保全情報をユーザに提示する健全性保全部と
を備える原子力発電プラントの健全性評価システム。 - 前記応力分布算出部は、同じ構造体が複数存在する場合において、各構造体に対して予め弾性解析を行い、弾性解析の結果が近似するものをグループ化して複数のグループを作成し、各前記グループにおいて前記構造体の弾塑性解析を行うことにより応力分布を得て、該グループと応力分布とを対応付けて格納したデータベースを有しており、
前記データベースから健全性の評価構造体の残留応力の応力分布を取得する請求項1に記載の原子力発電プラントの健全性評価システム。 - 前記応力分布算出部は、健全性の評価構造体の残留応力を降伏応力とみなして前記残留応力の応力分布を得る請求項1に記載の原子力発電プラントの健全性評価システム。
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