ASME STP-NU-051-1-2012 CODE COMPARISON REPORT for Class 1 Nuclear Power Plant Components《1级核电站部件的规范对照报表》.pdf
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1、STP-NU-051-1 CODE COMPARISON REPORTfor Class 1 Nuclear Power Plant ComponentsSTP-NU-051-1 CODE COMPARISON REPORT for Class 1 Nuclear Power Plant Components Prepared for: Multinational Design Evaluation Programme Codes and Standards Working Group Date of Issuance: December 31, 2012 This report is the
2、 result of a multinational effort by Standards Development Organizations (SDOs) from the United States of America, France, Japan, Korea, Canada and Russia. Neither ASME, ASME ST-LLC, the contributors, nor others involved in the preparation or review of this report, nor any of their respective employ
3、ees, members or persons acting on their behalf, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe upon privat
4、ely owned rights. Reference herein to any specific co mmercial product, process or service b y trade name, trademark, manufacturer or otherwise does not necessarily constitute or imply its endorsement, r ecommendation or favoring by ASME ST-LLC or others involved in the preparation or review of this
5、 report, or any agency thereof. The views and opinions of the authors, contributors, and reviewers of the report expressed herein do not necessarily reflect those of ASME ST-LLC or others involved in the preparation or review of this report, or any agency thereof. ASME ST-LLC does not take any posit
6、ion with respect to the validity of any patent rights asserted in connection with any items mentioned in this document, and does not undertake to insure anyone utilizing a publication against liability for infringement of any applicable Letters Patent, nor assumes any such liability. Users of a publ
7、ication are expressly advised that determination of the validity of any such patent rights, and the risk of infringement of such rights, are entirely their own responsibility. Participation by federal agency representative(s) or person(s) affiliated with industry is not to be interpreted as governme
8、nt or industry endorsement of this publication. ASME is the registered trademark of the American Society of Mechanical Engineers. No part of this document may be reproduced in any form, in an electronic retrieval system or otherwise, without the prior written permission of the publisher. ASME Standa
9、rds Technology, LLC Three Park Avenue, New York, NY 10016-5990 ISBN No. 978-0-7918-6868-3 Copyright 2012 by ASME Standards Technology, LLC All Rights Reserved Code Comparison Report STP-NU-051-1 iii Summary of Changes December 31, 2012 STP-NU-051-1 CODE COMPARISON REPORT for Class 1 Nuclear Power Pl
10、ant Components The following changes have been made to the first revision of STP-NU-051. Rev. 1 Page Location Change iv-xii Table of Contents Updated to reflect changes xiv Abstract Updated to reflect addition of NIKIET input 1-128 Report Body General editorial and formatting corrections 34 Added Se
11、ction 2.6 Added background information on NIKIET 46 Added Section 3.5 PNAE G-7 General Layout Comparison 129 Added Section 8 Added PNAE G-7 vs ASME BPVC III comparison 281 Appendix B2 Added JSME comparison for pumps, valves and piping 385 Appendix C2 Updated tables to correct formatting errors 454 A
12、ppendix E Added PNAE G7 Detailed Comparison Tables STP-NU-051-1 Code Comparison Report iv TABLE OF CONTENTS Foreword . xiii Abstract xiv 1 INTRODUCTION 1 1.1 Background and Scope . 1 1.2 Objectives . 1 1.3 Contents of the Report 1 1.4 Comparison Scale . 2 2 GENERAL PRESENTATION OF CODES 4 2.1 Backgr
13、ound Information on ASME . 4 2.2 Background Information on AFCEN . 9 2.3 Background Information on JSME. 15 2.4 Background Information on KEA 22 2.5 Background Information on CSA. 26 2.6 Background information on NIKIET . 34 3 GENERAL CODE LAYOUT COMPARISONS . 38 3.1 RCC-M versus ASME General Layout
14、 Comparison . 38 3.2 JSME versus ASME General Layout Comparison 40 3.3 KEPIC versus ASME General Layout Comparison . 43 3.4 CSA versus ASME General Layout Comparison 44 3.5 PNAE G-7 vs. ASME Code General Layout Comparison . 46 4 RCC-M VERSUS ASME BPVC SECTION III COMPARISON . 49 4.1 Abstract 49 4.2
15、Introduction 49 4.3 Preliminary Paragraphs and Scope Presentation 50 4.4 Materials . 52 4.5 Design 62 4.5.1 Piping, Valves, and Pumps . 65 4.6 Fabrication Welding 69 4.7 Examination . 78 4.8 Pressure Tests . 83 4.9 Overpressure Protection . 84 4.10 Overview of Quality Aspects . 86 4.11 Conclusion 87
16、 Code Comparison Report STP-NU-051-1 v TABLE OF CONTENTS (CONT.) 5 JSME VERSUS ASME BPVC SECTION III COMPARISON 90 5.1 Abstract 90 5.2 Introduction 90 5.3 Preliminary Paragraphs and Scope Presentation 92 5.4 Materials 92 5.5 Design 93 5.5.1 Piping, Valves, and Pumps . 96 5.6 Fabrication Welding . 10
17、1 5.7 Examination . 103 5.8 Pressure Tests 105 5.9 Overpressure Protection . 105 5.10 Overview of Quality Aspects . 106 5.11 Conclusion . 107 6 KEPIC VERSUS ASME BPVC SECTION III COMPARISON 111 6.1 Abstract 111 6.2 Introduction 111 6.3 Preliminary Paragraphs and Scope Presentation 112 6.4 Materials
18、113 6.5 Design 113 6.6 Piping, Valves, and Pumps 113 6.7 Fabrication Welding . 114 6.8 Examination . 114 6.9 Pressure Tests 114 6.10 Overpressure Protection . 114 6.11 Overview of Quality Aspects . 115 6.12 Conclusion . 118 7 CSA VERSUS ASME BPVC SECTION III COMPARISON 119 7.1 Abstract 119 7.2 Intro
19、duction 119 7.3 Preliminary Paragraphs and Scope Presentation 120 7.4 Materials 122 7.5 Design 123 7.5.1 Piping, Valves, and Pumps . 123 7.6 Fabrication Welding . 124 STP-NU-051-1 Code Comparison Report vi TABLE OF CONTENTS (CONT.) 7.7 Examination . 124 7.8 Pressure Tests . 125 7.9 Overpressure Prot
20、ection . 126 7.10 Overview of Quality Aspects . 127 7.11 Conclusion 127 8 PNAE G-7 VERSUS ASME BPVC Section III COMPARISON . 128 8.1 Abstract 128 8.2 Introduction 129 8.3 Preliminary Paragraphs and Scope Presentation 130 8.4 Materials . 131 8.5 Design 135 8.5.1 Classification of Equipment and Piping
21、 . 135 8.5.2 Classification of Service Levels 135 8.5.3 Nominal Allowable Stress (Design Stress Intensity) 136 8.5.4 Determination of Principal Dimensions (Analysis by Formula) 138 8.5.5 Stress Classification 140 8.5.6 Mechanical Loads Evaluation . 141 8.5.7 Buckling Analysis . 143 8.5.8 Ratcheting
22、Analysis 143 8.5.9 Fatigue Analysis . 144 8.5.10 Fast Fracture Analysis 148 8.6 Fabrication Welding 149 8.7 Examination . 152 8.7.1 Examination of Surface of Welded Edges 153 8.7.2 Radiographic Examination 153 8.7.3 Liquid Penetrant and Magnetic Particle Method 155 8.7.4 Ultrasonic Examination 155 8
23、.7.5 Convexity of Weld Seams 155 8.7.6 Offset of Weld Edges in Butt Weld Joints 156 8.8 Pressure Tests . 158 8.9 Overpressure Protection . 160 8.10 Overview of Quality Aspects . 161 8.10.1 Normative Legal Basis 161 8.10.2 Quality Assurance Programs. 161 8.10.3 Norms and Rules, “Requirements for repo
24、rt content about WWER type reactors (NP-006-98) safety justification (OOB NPP)” . 163 8.10.4 Conformance Evaluation in the Form of Tests . 163 8.10.5 Conformance Evaluation in the Form of State Control (Supervision) 163 8.10.6 Conformance Evaluation in the Form of Acceptance . 163 8.10.7 Conformance
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