Volumes | Pressure Vessels and Piping Conference | American Society of Mechanical Engineers Digital Collection

Topics: Cladding systems (Building) , Fatigue , Databases , Pipes , Anisotropy , Electromagnetic scattering , Fatigue design , Geometry , Heat , Manufacturing

Fatigue Behavior of Dissimilar Welds Used for Nuclear Piping

Karl-Heinz Herter, Xaver Schuler, Michael Hoffmann, Peter Kopp

PVP 2013; V01BT01A002doi:https://doi.org/10.1115/PVP2013-97400

Abstract

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Topics: Fatigue , Pipes , Welded joints , Steel , Nuclear power stations , Alloys , Design , Nickel , Safety , Temperature

The Simplified Method for Fatigue Assessment of the European Pressure Vessel Standard EN 13445

Fernando Lidonnici

PVP 2013; V01BT01A003doi:https://doi.org/10.1115/PVP2013-97568

Abstract

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Topics: Fatigue , Pressure vessels , Stress , Pressure , Design , Testing , Vessels , Welded joints , Cycles , Finite element methods

Effects of Strain Rate on the Very High Cycle Fatigue Properties of Low Alloy Steel SFVQ1A

Takashi Nakamura, Hiroyuki Oguma, Shingo Nukaya

PVP 2013; V01BT01A004doi:https://doi.org/10.1115/PVP2013-97756

Abstract

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Topics: Alloy steel , High cycle fatigue , Stress

Using the Nonlinear Kinematic Hardening Material Model of Chaboche for Elastic-Plastic Ratcheting Analysis

Arturs Kalnins, Jürgen Rudolph, Adrian Willuweit

PVP 2013; V01BT01A005doi:https://doi.org/10.1115/PVP2013-98150

Abstract

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Topics: Calibration , Hardening , Kinematics

Recent Developments in Chinese Codes and Standards

Development of Regulation on Accident Management and Statistics Analysis on Accident for China Special Equipment

Jingbiao Yang, Jiong Zheng, Weijian Luo, Xufeng Li

PVP 2013; V01BT01A006doi:https://doi.org/10.1115/PVP2013-97118

Abstract

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Topics: Accident management , Accidents , China , Statistics , Safety , Regulations

Research on Failure Mechanism of Carbon Fiber Composite Materials Basing on Acoustic Emission

Yan-Lei Liu, Wei-Zhong Li, Fu-Yong Xia, Bing Wang, Shu-Xin Han, Cheng-Dai He, Bing Yu

PVP 2013; V01BT01A007doi:https://doi.org/10.1115/PVP2013-97120

Abstract

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Topics: Acoustic emissions , Carbon fibers , Composite materials , Failure mechanisms , Laminates

Acoustic Emission Test of Pressure Vessel Leakage

Zhongzheng Zhang, Hua Liang, Cheng Ye, Wensheng Cai, Jun Jiang

PVP 2013; V01BT01A008doi:https://doi.org/10.1115/PVP2013-97126

Abstract

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Topics: Acoustic emissions , Leakage , Pressure vessels

Study on Wind-Induced Vibration of a Super-High Tower

Zhiwei Chen, Caifu Qian, Guoyi Yang, Xiang Li, Lijun Yin

PVP 2013; V01BT01A009doi:https://doi.org/10.1115/PVP2013-97166

Abstract

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Topics: Vibration , Vortex street , Wind

Tests and Discussions on the Impact Work of the S30403 Austenitic Stainless Steel at 20°C and -196°C

Zhiwei Chen, Guoyi Yang, Caifu Qian, Xiang Li, Haoyang Wang

PVP 2013; V01BT01A010doi:https://doi.org/10.1115/PVP2013-97167

Abstract

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Topics: Stainless steel , Temperature

Experimental Research of AE Inspection on Stress Corrosion Crack for Small Pressure Vessel

Zhongzheng Zhang, Hua Liang, Cheng Ye, Wensheng Cai, Jun Jiang

PVP 2013; V01BT01A011doi:https://doi.org/10.1115/PVP2013-97244

Abstract

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Topics: Acoustic emissions , Inspection , Pressure vessels , Stress corrosion cracking

Crack Growth Analysis of High-Pressure Equipment for Hydrogen Storage

Z. Y. Li, C. L. Zhou, Y. Z. Zhao, Z. L. Hua, L. Zhang, M. Wen, P. Xu

PVP 2013; V01BT01A012doi:https://doi.org/10.1115/PVP2013-97272

Abstract

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Topics: Fracture (Materials) , High pressure (Physics) , Hydrogen storage , Hydrogen , Cycles , Tensile strength , Pressure , Regulations , Fatigue cracks , Hydrogen embrittlement

Research on Acoustic Emission Signals Characteristics of Pitting Corrosion on 304 Stainless Steel

Zhongzheng Zhang, Hua Liang, Cheng Ye, Wensheng Cai, Jun Jiang, Qiang Cui

PVP 2013; V01BT01A013doi:https://doi.org/10.1115/PVP2013-97302

Abstract

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Topics: Acoustic emissions , Corrosion , Signals , Stainless steel , Temperature

Failure and Prevention of Pressure Vessels due to Instability of Process System

Xuedong Chen, Jianxin Zhu, Zhichao Fan, Zhibin Ai

PVP 2013; V01BT01A014doi:https://doi.org/10.1115/PVP2013-97320

Abstract

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Topics: Failure , Petrochemicals , Pressure vessels

Acoustic Emission Testing of High Strength Steel LPG Spherical Tanks

Jun Jiang, Rong Yi, Lili Que

PVP 2013; V01BT01A015doi:https://doi.org/10.1115/PVP2013-97333

Abstract

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Topics: Acoustic emission testing , Acoustic emissions , Fracture (Materials) , High strength steel

The Further Development of National Safety Assessment Standard for In-Service Pressure Equipment Containing Defects

Shanshan Shao, Guodong Jia, Liang Sun, Hui Wang

PVP 2013; V01BT01A016doi:https://doi.org/10.1115/PVP2013-97369

Abstract

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Topics: Pressure equipment , Safety , Fitness-for-service , Damage , Engineering standards

Development of Equipment Integrity Management System Based on Predictive Maintenance

Guodong Jia, Hui Wang, Xiang Li, Jiandong Zhong, Guoshan Xie, Weihua Wang

PVP 2013; V01BT01A017doi:https://doi.org/10.1115/PVP2013-97388

Abstract

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Topics: Maintenance

Experimental Investigation of the Strain-Strengthen Effect on the Existed I+II Mixed Mode Fatigue Crack Transformation Propagation in an Austenite Stainless Steel

Huifang Li, Zhenbei Wang, Xiaoju Sun, Caifu Qian

PVP 2013; V01BT01A018doi:https://doi.org/10.1115/PVP2013-97481

Abstract

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Topics: Fatigue cracks , Stainless steel , Fracture (Materials) , Compressive stress , Stress , Crack propagation , Displacement , Finite element analysis , Finite element methods

Time-History Analysis of a Super-Large Storage Tank Under Seismic Excitation

Fan Bu, Caifu Qian

PVP 2013; V01BT01A019doi:https://doi.org/10.1115/PVP2013-97541

Abstract

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Topics: Excitation , Storage tanks , Deformation , Earthquakes , Roofs , Sloshing , Finite element model , Fluids , Girders , Wind

Failure Analysis of Expansion Bellows Serving in Steam Pipe Network

Yichang Huang, Xiaoying Tang, Houde Yu, Yaozhou Qian, Ruqing Wu

PVP 2013; V01BT01A020doi:https://doi.org/10.1115/PVP2013-97556

Abstract

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Topics: Bellows (Equipment) , Failure analysis , Pipes , Steam , Hazardous substances , Fracture (Materials) , Cracking (Materials) , Failure , Fracture (Process) , Stress

Study on Structural Integrity Analysis of Tubular Reactor With Corrosion Pits in LDPE Plant

Jianping Zhao, Chunsheng Miao, Jiang Chen, Xinchun Guan

PVP 2013; V01BT01A021doi:https://doi.org/10.1115/PVP2013-97602

Abstract

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Topics: Corrosion , Finite element methods , Load bearing capacity , Pressure , Fatigue cracks , Petrochemicals , Safety

Optimization Analysis on the Structure Parameters of a 20×10⁴ m³ Ultra-Large Tank for Crude Oil Storage

Wenzhuo Feng, Zhiping Chen, Xinliang Shen, Fan Zhou, Haigui Fan

PVP 2013; V01BT01A022doi:https://doi.org/10.1115/PVP2013-97758

Abstract

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Topics: Crude oil , Optimization , Storage , Stress , Shells , Design , Stress concentration , Computer simulation , Finite element methods , Hoop stress

Study on Leakage Diffusion and Force Analysis of Double-Layer Structure of Oil Storage Tank

Liwei Zhao, Fujun Liu, Shuai Kong, Zhangwei Ling, Liqin Wang

PVP 2013; V01BT01A023doi:https://doi.org/10.1115/PVP2013-97842

Abstract

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Topics: Diffusion (Physics) , Leakage , Storage tanks , Computer simulation , Corrosion , Deformation , Design , Gasoline , Inspection , Pipelines

Study on Plastic Collapse Load of Steel Elliptical Heads Under Internal Pressure

Liang Sun, Guide Deng, Jiufeng Zhao

PVP 2013; V01BT01A024doi:https://doi.org/10.1115/PVP2013-97891

Abstract

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Topics: Collapse , Pressure , Steel , Stress , Constitutive equations , Design , Errors , Finite element analysis , Pressure vessels , Shapes

Numerical Study of Flow Induced Vibration of the Tube Bundle in a Lash Baffle Shell-and-Tube Heat Exchanger

Haiyang Sun, Caifu Qian

PVP 2013; V01BT01A025doi:https://doi.org/10.1115/PVP2013-98126

Abstract

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Topics: Flow-induced vibrations , Fluids , Heat exchangers , Shells , Vibration

Recent Developments in European Codes and Standards

Derivation of Design Fatigue Curves for Austenitic Stainless Steel Grades 1.4541 and 1.4550 Within the German Nuclear Safety Standard KTA 3201.2

Xaver Schuler, Karl-Heinz Herter, Jürgen Rudolph

PVP 2013; V01BT01A026doi:https://doi.org/10.1115/PVP2013-97138

Abstract

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Topics: Design , Fatigue , Safety , Stainless steel , Stress , Temperature

Validation of Plastic Collapse Assessments Using BS 7910:2013 and R6 Procedures

Şefika Elvin Eren, Tyler London, Yang Yang, Isabel Hadley

PVP 2013; V01BT01A027doi:https://doi.org/10.1115/PVP2013-97513

Abstract

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Topics: Collapse , Stress , Finite element analysis , Boundary-value problems , Fracture (Materials) , Fracture (Process) , Geometry , Plates (structures)

RCC-MRx — Addenda 2013: Feedback of Application of the Code — Developments of Rules to the Evolution of Projects Needs

C. Pétesch, T. Lebarbé, D. Bonne, F. de la Burgade, M. Blat-Yrieix

PVP 2013; V01BT01A028doi:https://doi.org/10.1115/PVP2013-97672

Abstract

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Topics: Feedback , Construction , Design , High temperature , Vacuum , Vessels

Guidelines for Managing the Integrity of Bolted Joints: Developments in European Standards

Robert Noble

PVP 2013; V01BT01A029doi:https://doi.org/10.1115/PVP2013-98012

Abstract

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Topics: Bolted joints , Leakage , Disasters , Ocean engineering

Standards, Specifications, Test Methods and Technical Reports for GRP Water, Drainage and Sewerage Piping

António Torres Marques

PVP 2013; V01BT01A030doi:https://doi.org/10.1115/PVP2013-98023

Abstract

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Topics: Drainage , Pipes , Water , Test facilities

Recent Developments in Japanese Codes and Standards

Development of Limit State Design for Fast Reactor by System Based Code

Daigo Watanabe, Yasuharu Chuman, Tai Asayama, Shigeru Takaya, Hideo Machida, Yoshio Kamishima

PVP 2013; V01BT01A031doi:https://doi.org/10.1115/PVP2013-97154

Abstract

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Topics: Design , Fast neutron reactors , Stress , Acceptance criteria , Design methodology , Plant design , Reactor vessels

Improvement of Jet Pump Inlet Mixer in Boiling Water Reactor for Mitigating Flow-Induced Vibration and Fouling

Masanobu Watanabe, Akio Sayano, Kunihiko Kinugasa, Hajime Mori, Tsuyoshi Hagiwara

PVP 2013; V01BT01A032doi:https://doi.org/10.1115/PVP2013-97235

Abstract

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Topics: Boiling water reactors , Flow-induced vibrations , Jet pumps , Damage , Flow (Dynamics) , Power uprate , Risk , Vibration , Ceramic coatings , Coating processes

Study on Evaluation Accuracy Required for Stress Intensity Factor Solution

Naoki Miura, Masaki Nagai, Masaki Shiratori

PVP 2013; V01BT01A033doi:https://doi.org/10.1115/PVP2013-97563

Abstract

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Topics: Stress , Fatigue cracks , Fracture (Materials) , ASME Boiler and Pressure Vessel Code , Fitness-for-service , Fracture mechanics , Japan Society of Mechanical Engineers , Nuclear power stations , Pipes , Surface cracks

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (2) Development of the Material Strength Standard of 316FR Stainless Steel

Takashi Onizawa, Yuji Nagae, Shigeru Takaya, Tai Asayama

PVP 2013; V01BT01A034doi:https://doi.org/10.1115/PVP2013-97608

Abstract

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Topics: Construction , Design , Fast neutron reactors , JSME Standards , Stainless steel , Strength (Materials) , Creep , Irradiation (Radiation exposure) , Japan Society of Mechanical Engineers , Low cycle fatigue

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (4) Creep–Fatigue Evaluation Method for Modified 9Cr–1Mo Steel

Shigeru Takaya, Yuji Nagae, Tai Asayama

PVP 2013; V01BT01A035doi:https://doi.org/10.1115/PVP2013-97609

Abstract

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Topics: Construction , Creep , Design , Evaluation methods , Fast neutron reactors , Fatigue , JSME Standards , Steel , Failure , Relaxation (Physics)

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (3) Development of the Material Strength Standard of Modified 9Cr-1Mo Steel

Takashi Onizawa, Yuji Nagae, Shigeru Takaya, Tai Asayama

PVP 2013; V01BT01A036doi:https://doi.org/10.1115/PVP2013-97611

Abstract

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Topics: Construction , Design , Fast neutron reactors , JSME Standards , Steel , Strength (Materials) , Creep , Boilers , Circuits , Coolants

Stress Intensity Factors for Cracks With Large Aspect Ratio in Cylinder

Yinsheng Li, Hiroaki Doi, Kunio Hasegawa, Kazuya Osakabe, Hiroshi Okada

PVP 2013; V01BT01A037doi:https://doi.org/10.1115/PVP2013-97665

Abstract

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Topics: Cylinders , Fracture (Materials) , Stress , Surface cracks , Nuclear power stations , Wall thickness , ASME Boiler and Pressure Vessel Code , Dimensions , Fitness-for-service , Flat plates

Fully Automated SCC and Fatigue Crack Propagation Analyses on Deep Semi-Elliptical Flaws

Kota Sugawara, Hirohito Koya, Hiroshi Okada, Yinsheng Li, Kazuya Osakabe, Hiroshi Kawai

PVP 2013; V01BT01A038doi:https://doi.org/10.1115/PVP2013-97678

Abstract

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Topics: Fatigue cracks , Crack propagation , Fracture (Materials) , Stress , Finite element analysis , Shapes , Anisotropy , Computation , Computer software , Finite element model

Development of Fatigue Assessment Method Based on Flaw Tolerance Concept

Seiji Asada, Takeda Shuhei, Taiji Hirasawa, Toshiyuki Saito, Itaru Saito, Koji Dozaki

PVP 2013; V01BT01A039doi:https://doi.org/10.1115/PVP2013-97773

Abstract

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Topics: Fatigue , Evaluation methods , Japan Society of Mechanical Engineers , Energy generation , JSME Standards , Nondestructive evaluation , Nuclear power

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (6) Design Margin Assessment for the New Materials to the Rules

Masanori Ando, Sota Watanabe, Koichi Kikuchi, Tomomi Otani, Kenichiro Satoh, Kazuyuki Tsukimori, Tai Asayama

PVP 2013; V01BT01A040doi:https://doi.org/10.1115/PVP2013-97803

Abstract

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Topics: Construction , Design , Fast neutron reactors , JSME Standards , Japan Society of Mechanical Engineers , Creep , Damage , Fatigue , Finite element analysis , Materials properties

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (5) Creep-Fatigue Evaluation Method for 316FR Stainless Steel

Yuji Nagae, Shigeru Takaya, Tai Asayama

PVP 2013; V01BT01A041doi:https://doi.org/10.1115/PVP2013-97806

Abstract

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Topics: Construction , Creep , Design , Evaluation methods , Fast neutron reactors , Fatigue , JSME Standards , Stainless steel , Failure , Rupture

Study on Minimum Wall Thickness Requirement of Reactor Vessel of Fast Reactor for Seismic Buckling by System Based Code

Shigeru Takaya, Daigo Watanabe, Shinobu Yokoi, Yoshio Kamishima, Kenichi Kurisaka, Tai Asayama

PVP 2013; V01BT01A042doi:https://doi.org/10.1115/PVP2013-97858

Abstract

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Topics: Buckling , Fast neutron reactors , Reactor vessels , Wall thickness , Reliability , Design methodology , Earthquake risk , Nuclear power stations , Optimization , Safety

Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Mini-CT Specimens

Tohru Tobita, Yutaka Nishiyama, Takuyo Ohtsu, Makoto Udagawa, Jinya Katsuyama, Kunio Onizawa

PVP 2013; V01BT01A043doi:https://doi.org/10.1115/PVP2013-97897

Abstract

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Topics: Fracture toughness , Reactor vessels , Steel , ASTM International , Brittleness , Phase transition temperature , Shapes , Temperature

Structural Integrity Evaluation of Reactor Pressure Vessels During PTS Events Using Deterministic and Probabilistic Fracture Mechanics Analysis

Kazuya Osakabe, Hiroyuki Nishikawa, Koichi Masaki, Jinya Katsuyama, Kunio Onizawa

PVP 2013; V01BT01A044doi:https://doi.org/10.1115/PVP2013-97923

Abstract

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Topics: Fracture mechanics , Reactor vessels , Design for Manufacturing , Fracture (Materials) , Accidents , Coolants , Fracture toughness , Probability , Reliability , Steam

A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens — 2nd Report: Fracture Toughness Comparison in Specified Loading Rate Condition

Masato Yamamoto, Kunio Onizawa, Kentaro Yoshimoto, Takuya Ogawa, Yasuhiro Mabuchi, Naoki Miura

PVP 2013; V01BT01A045doi:https://doi.org/10.1115/PVP2013-97936

Abstract

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Topics: Fracture toughness , Deformation , Electromagnetic scattering , Steel , Surveillance , Dimensions , Governments , Reliability , Temperature

Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors: (1) Overview

Tai Asayama, Koji Dozaki, Tomomi Otani, Takanari Inatomi, Masanori Ando

PVP 2013; V01BT01A046doi:https://doi.org/10.1115/PVP2013-98061

Abstract

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Topics: Construction , Design , Fast neutron reactors , JSME Standards , Japan Society of Mechanical Engineers , Breeder reactors , Carbon , Creep , Engineering prototypes , Evaluation methods

High Fluence Surveillance Data and Recalibration of RPV Embrittlement Correlation Method in Japan

Naoki Soneda, Kenichi Nakashima, Kenji Nishida, Kenji Dohi

PVP 2013; V01BT01A047doi:https://doi.org/10.1115/PVP2013-98076

Abstract

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Topics: Embrittlement , Fluence (Radiation measurement) , Surveillance , Steel , Databases , Irradiation (Radiation exposure) , Neutrons , Reactor vessels

Alternative Reference Temperature Based on Master Curve Approach in Japanese Reactor Pressure Vessel Steel

Takatoshi Hirota, Takashi Hirano, Kunio Onizawa

PVP 2013; V01BT01A048doi:https://doi.org/10.1115/PVP2013-98164

Abstract

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Topics: Reactor vessels , Steel , Temperature , Fracture toughness , ASTM International , Base metals , Metals , Nuclear power stations , Safety

Repair, Replacement and Mitigation for Fitness-for-Service Rules

Advanced Inlay System for Inlet/Outlet Nozzles of RV for Preventive Maintenance Against Alloy 600 PWSCC in Japanese PWR Plants

Kazuhide Yamamoto, Masahiko Kizawa, Hiroki Kawazoe, Yuki Kobayashi, Ken Onishi, Daisaku Hase

PVP 2013; V01BT01A049doi:https://doi.org/10.1115/PVP2013-97089

Abstract

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Topics: Alloys , Maintenance , Nozzles , Pressurized water reactors , Heat , Shot peening , Stress , Water , Welding , Accidents

Crack Growth Behavior and Preventive Maintenance for Reactor Internals With Cracks in Tokai-2 Nuclear Power Plant

Takushi Fujino, Takeshi Terakado, Koji Dozaki, Nobuo Ito, Kunihiro Hasegawa

PVP 2013; V01BT01A050doi:https://doi.org/10.1115/PVP2013-97257

Abstract

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Topics: Fracture (Materials) , Maintenance , Nuclear power stations , Inspection , Japan Society of Mechanical Engineers , Shapes , Crack propagation , Cycles , Metals , Shot peening

Reliability of Water Jet Peening as Residual Stress Improvement

Yusuke Kono, Koji Okimura, Rebecca Toth, Tomonobu Sato, Masakazu Tajima, Cecile Jardin, Philippe Le-Bec

PVP 2013; V01BT01A051doi:https://doi.org/10.1115/PVP2013-97405

Abstract

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Topics: Reliability , Shot peening , Stress , Water , Alloys , Compressive stress , Countermeasures , Instrumentation , Lasers , Metals

Evaluation for Nondestructive Crack Sizing Capability on Cracked Surface Treated by Water Jet Peening

Ryuji Kimura, Fujio Yoshikubo, Kazuya Ehara, Nobuo Murakami, Akihiro Kanno

PVP 2013; V01BT01A052doi:https://doi.org/10.1115/PVP2013-97652

Abstract

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Topics: Fracture (Materials) , Shot peening , Water , Crack propagation , Nuclear power stations , Pressurized water reactors , Ultrasonic testing , Alloys , Compression , Eddy current testing

Structural Integrity of Pressure Components

Performance Study of the Simplified Theory of Plastic Zones for the Fatigue Check

Hartwig Hübel, Adrian Willuweit, Jürgen Rudolph, Rainer Ziegler, Hermann Lang, Klemens Rother, Simon Deller

PVP 2013; V01BT01A053doi:https://doi.org/10.1115/PVP2013-97137

Abstract

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Topics: Fatigue , Fatigue analysis , Stress , Elastic analysis , Cycles , Plasticity

Structural Integrity for Nuclear Power Plant Against Excessive Load on Design Extension Condition

Daigo Watanabe, Kiminobu Hojo

PVP 2013; V01BT01A054doi:https://doi.org/10.1115/PVP2013-97160

Abstract

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Topics: Design , Nuclear power stations , Stress , Acceptance criteria , Light water reactors , Safety

PWR and WWER Steam Generator Tube Integrity Assessment

Roman Krautschneider

PVP 2013; V01BT01A055doi:https://doi.org/10.1115/PVP2013-97269

Abstract

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Topics: Boilers , Pressurized water reactors , Design , Inspection , Maintenance

Evaluation on Constraint Effect of Reactor Pressure Vessel Under Pressurized Thermal Shock

Naoki Ogawa, Kentaro Yoshimoto, Takatoshi Hirota, Shohei Sakaguchi, Toru Oumaya

PVP 2013; V01BT01A056doi:https://doi.org/10.1115/PVP2013-97566

Abstract

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Topics: Reactor vessels , Thermal shock , Fracture (Materials) , Fracture toughness , Accidents , Stress , Surface cracks , Coolants , Deformation , Finite element analysis

Integrity Evaluation of Korean Nuclear Reactor Pressure Vessel Under Pressurized Thermal Shock Conditions According to JEAC

Se-Chang Kim, Jae-Boong Choi, Doo-Ho Cho, Sang-Min Lee, Yong-Beum Kim, Hae-Dong Chung

PVP 2013; V01BT01A057doi:https://doi.org/10.1115/PVP2013-97687

Abstract

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Topics: Nuclear reactors , Pressure vessels , Thermal shock , Coolants , Accidents , Finite element analysis , Finite element model , Fluence (Radiation measurement) , Fracture mechanics , Fracture toughness

Investigation on Constraint Effect of a Reactor Pressure Vessel Subjected to Pressurized Thermal Shocks

Guian Qian, Markus Niffenegger

PVP 2013; V01BT01A058doi:https://doi.org/10.1115/PVP2013-98161

Abstract

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Topics: Fracture mechanics , Reactor vessels , Thermal shock

Technical Harmonization and Emerging Codes and Standards

MOP, MAOP, DP and MAWP: Understanding the Differences to Avoid Unnecessary Costs

John J. Aumuller, Vincent A. Carucci

PVP 2013; V01BT01A059doi:https://doi.org/10.1115/PVP2013-97086

Abstract

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Topics: ASME Standards , Design , Engineering standards , Pipelines , Pipes , Pressure , Pressure vessels , Safety , Stress

Bench-KJ: Benchmark on Analytical Calculation of Fracture Mechanics Parameters KI and J for Cracked Piping Components — Progress of the Work

S. Marie, C. Faidy

PVP 2013; V01BT01A060doi:https://doi.org/10.1115/PVP2013-97178

Abstract

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Topics: Fracture mechanics , Pipes , Stress , American Petroleum Institute , Cladding systems (Building) , Cylinders , Design , Finite element methods , Fracture (Materials) , Geometry

Comparison of Design Requirements for Nuclear Steam Generators in the ASME and RCC-M Codes

Junjie Cao, Peter Caple

PVP 2013; V01BT01A061doi:https://doi.org/10.1115/PVP2013-97438

Abstract

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Topics: Design , Nuclear reactor steam generators , Boilers , ASME Standards , Nuclear power stations , Pressure , ASME Boiler and Pressure Vessel Code

Stresses in Nozzle Shell Junctions due to External Loads: A Comparative Study

Dipak K. Chandiramani, Suresh K. Nawandar, Shyam Gopalakrishnan

PVP 2013; V01BT01A062doi:https://doi.org/10.1115/PVP2013-97532

Abstract

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Topics: Junctions , Nozzles , Shells , Stress , Finite element analysis , Finite element methods , Analytical methods , Computer software , Design , Geometry

Case Studies in Local Heat Treatment of Pressure Vessels Applying WRC-452 Principles

George Miller, Kenneth Kirkpatrick, Les P. Antalffy

PVP 2013; V01BT01A063doi:https://doi.org/10.1115/PVP2013-97645

Abstract

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Topics: Heat treating (Metalworking) , Pressure vessels , Heat , Heating , Welded joints , ASME Boiler and Pressure Vessel Code , Base metals , Furnaces , Metals , Temperature gradient

Use of Nuclear Mechanical Design Codes and Fracture Mechanics Procedures for the UK EPR™ at Hinkley Point C

Martin Gallegillo, Andrew Goodfellow, Christophe Philipp, Lol Miles, Anthony Williams

PVP 2013; V01BT01A064doi:https://doi.org/10.1115/PVP2013-97696

Abstract

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Topics: Design engineering , Fracture mechanics , Safety , Design , Inspection , ASME Standards , Engineering standards , Failure , Fracture (Materials) , Fracture (Process)

Technical Basis for Proposed Code Case of Alternative Rules for Cladding Repair by Underwater Electrochemical Deposition in Class 1 and 2 Applications

Myong-Jin Kim, Dong Jin Kim, Joung Soo Kim, Hong Pyo Kim, Seong Sik Hwang

PVP 2013; V01BT01A065doi:https://doi.org/10.1115/PVP2013-97857

Abstract

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Topics: Cladding systems (Building) , Maintenance , Reactor vessels , Alloy steel , Boilers , Carbon , Carbon steel , Corrosion , Accidents , Adhesion

International Harmonisation: A Key Challenge for Mechanical Components Codes and Standards

Claude Faidy

PVP 2013; V01BT01A066doi:https://doi.org/10.1115/PVP2013-97968

Abstract

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Topics: Engineering standards , Design , Manufacturing , Regulations , Japan Society of Mechanical Engineers , Licensing , Nondestructive evaluation , Pressure , Safety , Vessels

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Structural Integrity of Pressure Components

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