Effects of Simulated Seismic Loading on LBB Assessment of High Energy Piping

Author:

Gupta Suneel K.1,Bhasin Vivek1,Vaze K. K.1,Ghosh A. K.1,Kushwaha H. S.1

Affiliation:

1. Bhabha Atomic Research Center, Reactor Safety Division, Hall-7, Mumbai, 400 085, India

Abstract

The current Leak Before Break (LBB) assessment is based primarily on the monotonic fracture tearing instability. In it the maximum design accident load is compared with the fracture-tearing resistance load. The effect of cyclic loading has not been generally considered in the fracture assessment of nuclear power plant piping. It is a well-known fact that reversible cyclic loading decreases the fracture resistance of the material, which leads to increased crack growth. Indian nuclear power reactors consider Operational-Basis-Earthquake (OBE) and Safe-Shutdown-Earthquake (SSE) events in the design of various structures, systems, and components. Keeping this in view a series of cyclic tearing tests have been conducted on straight pipes, made of ASTM SA333 Gr.6 carbon steel. This is the material of primary heat transport (PHT) piping material of Indian Pressurized Heavy Water Reactors (PHWR). In this series 13 tests have been carried out circumferentially through wall cracked seamless and circumferential seam welded straight pipes under reversible cyclic bending loading. All the tests have been conducted under quasistatic, i.e., slow loading rates and dynamic inertia effects are not considered. The cyclic test results have been compared with the corresponding monotonic pipe fracture test results. These test results and its comparison with corresponding monotonic tearing clearly illustrate the need of addressing the reduction in apparent fracture toughness of material under reversible cyclic loading and the safe number of load cycles in the LBB assessment.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference16 articles.

1. Report of the U.S. Nuclear Regulatory Commission Piping Review Committee, 1984, “Evaluation of Postulated Pipe Breaks,” NUREG-1061, Vol. 3, Prepared by the Pipe Break Task Group.

2. International Atomic Energy Agency, 1993, “Applicability of the Leak Before Break Concept,” IAEA-TECDOC 710, Report of the IAEA Extra Budgetary Program on the Safety of WWER-440 Model-230 Nuclear Power Plants.

3. International Atomic Energy Agency, 1994, “Guidance for the Application of the Leak Before Break Concept,” IAEA-TECDOC 774, Report of the IAEA Extra Budgetary Program on the Safety of WWER-440 Model-230 Nuclear Power Plants.

4. Scott, P., Wilson, M., Olson, R., Marschall, C., Schmidt, R., and Wilkowski, G., 1994, “Stability of Cracked Pipe Under Inertial Stresses,” NUREG/CR-6233, Vol. 1, Report prepared for the U.S. Nuclear Regulatory Commission.

5. Kramer, G., Vieth, P., Marschall, C., Francini, R., and Wilkowski, G., 1997, “Stability of Cracked Pipe under Seismic/Dynamic Displacement-Controlled Stresses,” NUREG/CR-6233, Vol. 2, Report prepared for the U.S. Nuclear Regulatory Commission.

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线,采集、加工和组织学术论文而形成的新型学术文献查询和分析系统,可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容,当前同舟云学术共收录了国内外主流学术期刊6万余种,收集的期刊论文及会议论文总量共计约1.5亿篇,并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询!咨询电话:010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号  京ICP备18003416号-3