Volume 6A: Materials and Fabrication最新文献_第9页

Assessment of the Fitness for Service of the Flamanville EPR Reactor Pressure Vessel Closure Head and Bottom Head Domes Containing a Segregation Zone Characterized by a High Carbon Content Flamanville EPR反应堆压力容器封闭封头和含高碳含量分离区的底封头圆顶的适用性评估

Volume 6A: Materials and Fabrication Pub Date : 2018-07-15 DOI: 10.1115/PVP2018-84132

I. Delvallée-Nunio, O. Loiseau, D. Monhardt, Audrey Buiron, F. Dubois

{"title":"Assessment of the Fitness for Service of the Flamanville EPR Reactor Pressure Vessel Closure Head and Bottom Head Domes Containing a Segregation Zone Characterized by a High Carbon Content","authors":"I. Delvallée-Nunio, O. Loiseau, D. Monhardt, Audrey Buiron, F. Dubois","doi":"10.1115/PVP2018-84132","DOIUrl":"https://doi.org/10.1115/PVP2018-84132","url":null,"abstract":"To complete the manufacturing process qualification of the closure head and bottom head domes of the Flamanville EPR RPV in 16MND5 ferritic steel (similar to A508 cl3), AREVA NP performed in 2014 material testing on a sacrificial dome so-called UA Sup. These tests revealed that the Charpy impact energy at 0°C — in the positive segregation zone at ¼ thickness — was lower than 60 J, the minimum value required by the French regulation. Thereafter, this result was explained by the high carbon content close to 0.3 % — against 0.18 % in the ladle — due to the forging process. The positive segregation was insufficiently eliminated to avoid high carbon content in certain location.\u0000 As the level of Charpy impact energy is an indicator of the level of fracture toughness, a thorough material characterization of the segregation zone, as well as a brittle fracture analysis have been proposed and carried out by AREVA NP to demonstrate that the Flamanville EPR RPV domes are tough enough for a safe operation.\u0000 The principles of the demonstration approach were reviewed by ASN and IRSN in 2015 and the final safety case was submitted to the ASN and IRSN review in December 2016. The latter led to the conclusion that, even if the segregation zone fracture toughness is lowered in comparison to that of the acceptance test zone, this does not put into question the Flamanville EPR RPV fitness for service as long as adequate in-service inspection of the domes is periodically performed.\u0000 This paper aims at presenting the key elements of the IRSN assessment from part of which this conclusion was drawn, namely the material testing program, the description of the loadings in normal and accidental conditions, and the brittle fracture analysis.","PeriodicalId":428760,"journal":{"name":"Volume 6A: Materials and Fabrication","volume":"4 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124542835","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Mismatch Effect on the Mode II Type Crack Tip Field in Power-Law Creeping Materials 幂律蠕变材料II型裂纹尖端场的错配效应

Volume 6A: Materials and Fabrication Pub Date : 2018-07-15 DOI: 10.1115/PVP2018-84623

Yanwei Dai, Yinghua Liu, Y. J. Chao

{"title":"Mismatch Effect on the Mode II Type Crack Tip Field in Power-Law Creeping Materials","authors":"Yanwei Dai, Yinghua Liu, Y. J. Chao","doi":"10.1115/PVP2018-84623","DOIUrl":"https://doi.org/10.1115/PVP2018-84623","url":null,"abstract":"The mismatch effect in weldments are widely to be seen in engineering practices. In this paper, the material mismatch effect on the mode II creep crack tip field is investigated and discussed. The effects of material mismatch and heat affected zone (HAZ) width on the C(t)-integral are presented. Both the local mismatch effect and the general mismatch effect are found to play important roles in the variations of C(t)-integral. The mismatch effect on the stress field of the mode II creep crack is also studied. The two-order term solutions are presented to characterize the material mismatch constraint effect on the mode II type creep crack. Some typical cases by considering general mismatch effect and local mismatch effect are given so as to make comparisons between the HRR field, FE solutions and the two-order term solutions. It can be seen that the two-order term solutions can coincide with the FE solutions quite reasonably regardless of creep extent, creep exponent, mismatch factor and HAZ width. This research also reveals the significant effect of the material mismatch on the high order term solutions under various conditions for mode II creep crack.","PeriodicalId":428760,"journal":{"name":"Volume 6A: Materials and Fabrication","volume":"18 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127781629","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1

Weld Residual Stress Activities Within the ATLAS+ Project ATLAS+项目中的焊接残余应力活动

Volume 6A: Materials and Fabrication Pub Date : 2018-07-15 DOI: 10.1115/PVP2018-84633

Michael C. Smith

引用次数: 1

Flamanville EPR RPV’s Heads Carbon Segregation: Vessel Heads Manufacturing Flamanville EPR RPV的头部碳分离:容器头部制造

Volume 6A: Materials and Fabrication Pub Date : 2018-07-15 DOI: 10.1115/PVP2018-84492

Benoit Lefever, S. Marie, T. Berger, Isabelle Vastra

引用次数: 2

Perspectives on Safety Margin Associated With Internal Repair of Buried Class 2 and 3 Safety Related Piping Using Carbon Fiber Reinforced Polymer Composites 碳纤维增强聚合物复合材料埋地2级和3级安全相关管道内部修复的安全裕度展望

Volume 6A: Materials and Fabrication Pub Date : 2018-07-15 DOI: 10.1115/PVP2018-84972

M. Uddin, P. Krishnaswamy, C. Basavaraju, K. Manoly

{"title":"Perspectives on Safety Margin Associated With Internal Repair of Buried Class 2 and 3 Safety Related Piping Using Carbon Fiber Reinforced Polymer Composites","authors":"M. Uddin, P. Krishnaswamy, C. Basavaraju, K. Manoly","doi":"10.1115/PVP2018-84972","DOIUrl":"https://doi.org/10.1115/PVP2018-84972","url":null,"abstract":"Carbon fiber reinforced polymer (CFRP) composites have been used for decades in various industries such as aerospace, oil and gas, and transportation mainly due to their high strength-to-weight-ratio and excellent corrosion resistance. However, the use of CFRP in nuclear industry applications has been very limited. Recently, a new ASME Boiler and Pressure Vessel (BPV) Code Case N-871 has been proposed for internal repair of buried Class 2 and 3 nuclear safety related piping using CFRP for Service Levels A, B, C and D at temperatures not exceeding 200F. This is a first-of-a-kind CFRP application for nuclear safety related piping.\u0000 It is known that CFRP materials are subject to property degradation due to environmental exposure as well as creep behavior under sustained loading. These factors should be considered when designing the CFRP repair for any nuclear safety related piping application to ensure an adequate safety margin is maintained. In the proposed Code Case, there are provisions for using two different design (analysis method) methods — Allowable Stress Design (ASD) and Load and Resistance Factor Design (LRFD) methods. The LRFD method has been widely used in civil engineering applications but has never been used in ASME Section III Code for nuclear piping applications. This paper presents a comparison of these two methods from a safety margin point of view. As CFRP is a new material for ASME BPV Code for nuclear safety related applications, several areas have been identified in the design concepts to ensure an adequate safety margin for Service Levels A, B, C and D. An effort is also made to provide guidelines on the required safety margin for CFRP repair of safety related piping. Finally, Code Case N-871 is reviewed to evaluate the minimum safety margin available for both ASD and LRFD methods.","PeriodicalId":428760,"journal":{"name":"Volume 6A: Materials and Fabrication","volume":"5 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"115461104","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

FA3 RPV Carbon Segregation Issue: Representativeness and Transferability of Sacrificial Parts FA3 RPV碳偏析问题:牺牲部件的代表性和可转移性

Volume 6A: Materials and Fabrication Pub Date : 2018-07-15 DOI: 10.1115/PVP2018-84487

A. Lefrançois, T. Berger, Benoit Lefever, S. Marie

{"title":"FA3 RPV Carbon Segregation Issue: Representativeness and Transferability of Sacrificial Parts","authors":"A. Lefrançois, T. Berger, Benoit Lefever, S. Marie","doi":"10.1115/PVP2018-84487","DOIUrl":"https://doi.org/10.1115/PVP2018-84487","url":null,"abstract":"In order to demonstrate that the cover head and bottom head of the FA3 Reactor Pressure Vessel (RPV) exhibits sufficient toughness to withstand operational (from normal up to faulted) conditions, a dedicated experimental program was performed for three sacrificial forged parts (two cover heads and a bottom head) manufactured in Creusot Forge as-well, according to a similar process.\u0000 In order to be allowed to consider the mechanical properties (toughness) measured on these sacrificial parts, it was necessary to prove that they were representative of the FA3 ones.\u0000 Among all the parameters influencing the toughness properties it was defined that two of them had a major impact: the carbon content and the quenching effects.\u0000 For the first one, it was identified that it could be influenced by pouring conditions, forging conditions, including discard and upsetting ratios and machining (thickness).\u0000 For the second one, it was identified that it could be influenced by post-heat treatment machining and by quenching conditions.\u0000 Regarding these factors, for the five parts: manufacturing parameters and acceptance test results were compared, taking into account uncertainties.\u0000 In addition, for the three sacrificial parts, carbon content measured for various depths in the thickness were compared, after a transformation methodology allowing to convert depth inside part to ingot vertical location.\u0000 Finally, it was shown that the sacrificial parts could be considered to be representative of the FA3 parts to be used, for their mechanical properties.","PeriodicalId":428760,"journal":{"name":"Volume 6A: Materials and Fabrication","volume":"3 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127424960","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 1

Compact Crack Arrest Tests for the Validation of a Finite Element Material Model of the Reactor Pressure Vessel Steel of the Nuclear Power Plant KKG KKG核电站反应堆压力容器钢有限元材料模型验证的紧凑止裂试验

Volume 6A: Materials and Fabrication Pub Date : 2018-07-15 DOI: 10.1115/PVP2018-84068

U. Mayer, Alexander Mutz, T. Nicak

{"title":"Compact Crack Arrest Tests for the Validation of a Finite Element Material Model of the Reactor Pressure Vessel Steel of the Nuclear Power Plant KKG","authors":"U. Mayer, Alexander Mutz, T. Nicak","doi":"10.1115/PVP2018-84068","DOIUrl":"https://doi.org/10.1115/PVP2018-84068","url":null,"abstract":"The integrity of a reactor pressure vessel (RPV) has to be given for its operating time in accordance with the regulations. An assessment of the RPV against brittle failure needs to be conducted specially for one of the most severe loading cases. This is the loss-of-coolant accident (LOCA). Cold water is injected into the RPV at operating conditions. This thermal shock of the ferritic pressure vessel wall leads to loading conditions at the beltline area known as Pressurized Thermal Shock (PTS).\u0000 The assessment against brittle failure is based on a deterministic fracture analysis. Common parameters like stress intensity factors are employed to calculate the PTS event for an assumed (postulated) flaw. Subsequently the results of the fracture mechanics analysis are compared with material properties obtained from the irradiation surveillance program of the RPV to demonstrate the exclusion of brittle fracture initiation.\u0000 The validation considers the material data and the velocity of the crack growing into the specimen until it stops. The measured crack propagation velocity for tests performed according to ASTM E1221 [1] is compared to the result of the Finite Element (FE) simulation of a Compact Crack Arrest (CCA) test.\u0000 For five of eight tests performed at −60 °C crack propagation velocity values were determined ranging from 509 m/s to 694 m/s with an average value of 618 m/s.","PeriodicalId":428760,"journal":{"name":"Volume 6A: Materials and Fabrication","volume":"7 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2018-07-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126715891","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 2

Analysis of Creep Crack Growth Behavior of the Brazed Joint Using Continuum Damage Mechanics Approach 用连续损伤力学方法分析钎焊接头蠕变裂纹扩展行为

Volume 6A: Materials and Fabrication Pub Date : 2018-07-15 DOI: 10.1115/PVP2018-85126

YuCai Zhang, Wenchun Jiang, S. Tu, Xian‐Cheng Zhang, Guo-Yan Zhou

引用次数: 1

Flamanville EPR RPV’s Heads Carbon Segregation: Characterization of the Segregation in the Heads Flamanville EPR RPV的头部碳偏析:头部偏析的表征

Volume 6A: Materials and Fabrication Pub Date : 2018-07-15 DOI: 10.1115/PVP2018-84495

P. Fichot, O. Calonne, M. Segond, S. Marie, Y. Desnoyers, M. Hajjaj, C. Miller

引用次数: 1

A Study on the Fracture Toughness at Different Locations of SMAW Welded Joint of Primary Coolant Piping 一次冷却剂管道SMAW焊接接头不同位置断裂韧性研究

Volume 6A: Materials and Fabrication Pub Date : 2018-07-15 DOI: 10.1115/PVP2018-84422

Weiwei Yu, Min-yu Fan, Jinhua Shi, F. Xue, Mingya Chen, Xu Chen

引用次数: 0