ASPECTS OF DESIGN CODES FOR METALLIC HIGH-TEMPERATURE COMPONENTS

被引:7
作者
NICKEL, H
SCHUBERT, F
PENKALLA, HJ
BREITBACH, G
机构
[1] Forschungszentrum Juelich GmbH, Institut für Reaktorwerkstoffe, D5170 Juelich
关键词
D O I
10.1016/0308-0161(91)90098-M
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
High temperature component design is very important in different industrial fields. This paper discusses work done in Germany on the design of metallic components for the Helium Cooled High Temperature Reactor. Candidate materials for application at the different temperature regions are presented. Criteria are developed to specify the allowable strength values of the materials (S(m), S(t)) for use in design codes. The following typical relevant phenomena are treated and discussed: -creep under uniaxial and multiaxial conditions up to temperatures of 1000-degrees-C; -creep fatigue interaction, where holding times during the stress strain cycles have a great influence on the life time; -creep buckling for pressure loaded shells with initial imperfections; -creep ratcheting as a phenomenon, where cyclic secondary stresses produce enhanced deformations; -fracture mechanics at high temperatures with the aspects of creep crack growth and fatigue crack growth.
引用
收藏
页码:167 / 192
页数:26
相关论文
共 20 条
[1]  
Post, Wirtz, Nickel, Rittenhouse, Kondo, Special Issue on High Temperature Gas Cooled Reactor Materials, Nuclear Technology, 66, (1984)
[2]  
Nickel, Hofmann, Wachholz, Weisbrodt, The helium-cooled high temperature reactor in the Federal Republic of Germany: safety features, integrity concept, outlook for design codes and licensing procedures, Symposium on Regulatory Practices and Safety Standards for Nuclear Power Plants, (1988)
[3]  
Breitbach, Schubert, Nickel, Proceedings of the Workshop on Structural Design Criteria for HTR, Jül-Conf 71, (1989)
[4]  
Nickel, Et al., Erarbeitung von Grundlagen zu einem Regelwerk über die Auslegung von HTR-Komponenten für Anwendungstemperaturen oberhalb 800°C (BMI-Vorhaben SR 191), Jül.-Spez.-248, (1984)
[5]  
Penkalla, Die Werkstoffdatenbank der Entwicklungsgemeinschaft Hochtemperaturreaktor, VDI-Berichte Nr. 600·4, pp. 283-303, (1987)
[6]  
Jansing, Teubner, Harth, Experience gained from the eva II and KVK operation, Nuclear Engineering and Design, 121, 2, pp. 173-182, (1990)
[7]  
Rabotnow, Creep Problems in Structural Members, (1969)
[8]  
Hechmer, Hollinger, The ASME Code and 3D stress evaluation, post conference Smirt-10, (1989)
[9]  
Bree, Elastic-plastic behaviour of thin tubes subjected to internal pressure and intermittent high-heat fluxes with application to fast-nuclear-reactor fuel elements, The Journal of Strain Analysis for Engineering Design, 2, 3, pp. 226-283, (1967)
[10]  
Breitbach, Schubert, Seehafer, Nickel, Experimental and theoretical work for the analysis of creep ratcheting and creep buckling of HTR components, Proceedings of a IAEA Specialist Meeting at Cracow, (1989)