Materials Property Requirements for Steam Generator Components in the Creep Range-Reference-Cited by-同舟云学术

Materials Property Requirements for Steam Generator Components in the Creep Range

Published:1981-11 Issue:2 Volume:55 Page:332-338
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Wood D. S.¹

Affiliation:

1. United Kingdom Atomk Energy Authority, Risley Nuclear Laboratories, Risley, Warrington, Cheshire WAS 6AT United Kingdom

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT55-332

Reference7 articles.

1. “ASME Nuclear Components Code Case N-47-14” p. 151, American Society of Mechanical Engineers.

2. H. P. OFFER, H. J. BURBOOM, and P. J. RING, “Final Summary Report on Characterisation of CRBRP Steam Generator Tubing,” GEFR-00378, General Electric Company (1978).

3. R. L. KLUEH, “Thermal Ageing Effects on the Mechanical Properties of Annealed 2¼Cr-lMO Steel,” ORNL·5324, Oak Ridge National Laboratory (1977).

4. P. P. PIZZO and G. L. MANDURRAGO, “Thermal Ageing Characteristics of CRBR Steam Generator Tubing,” GEFR-00474, General Electric Company (1979).

5. The effect of aging and cold working on the high-temperature low-cycle fatigue behavior of alloy 800H: Part I. The effect of hardening processes on the initial stress-strain curve

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. A toughness study of the weld heat-affected zone of a 9Cr–1Mo steel;Materials Characterization;2002-02

2. Effect of matrix hardness on the creep properties of a 12CrMoVNb steel;Metallurgical and Materials Transactions A;1999-09

3. Comparison of effects of aging on fracture of 9Cr–1Mo and 2·25Cr–1Mo steel Part 1 Quenched and tempered material;Materials Science and Technology;1991-03

4. The nucleation and growth of voids at carbides in 9 Cr-1 Mo steel;Acta Metallurgica;1986-07