Correlation of Transient-Test Data with Conventional Mechanical Properties Data-Reference-Cited by-同舟云学术

Correlation of Transient-Test Data with Conventional Mechanical Properties Data

Published:1975-03 Issue:3 Volume:25 Page:531-540
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Straalsund J. L.¹,Fish R. L.¹,Johnson G. D.¹

Affiliation:

1. Westinghouse Hanford Company, Hanford Engineering Development Laboratory P.O. Box 1970, Richland, Washington 99352

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/NT75-A24390

Reference3 articles.

1. C. W. HUNTER and R. L. FISH, “Deformation and Failure of Fast Reactor Cladding During Simulated Loss-of-Flow Type Transients,” HEDL-SA 645, Hanford Engineering Development Laboratory (1974).

2. M. M. PAXTON, “Mechanical Properties of Proto-typic FTR Cladding—20% C. W. Type 316 Stainless Steel Tubing,” HEDL-TME 71-59, Hanford Engineering Development Laboratory (1971).

Cited by 20 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. Formulation of high-temperature strength equation of 9Cr-ODS tempered martensitic steels using the Larson–Miller parameter and life-fraction rule for rupture life assessment in steady-state, transient, and accident conditions of fast reactor fuel;Journal of Nuclear Materials;2024-05

2. Ultra-high temperature creep rupture and transient burst strength of ODS steel claddings;Journal of Nuclear Materials;2019-04

3. Axial crack resistance of cladding tubes for fast reactors;Annals of Nuclear Energy;2017-12

4. Aging effect on the thermal transient behavior of the fuel cladding of a sodium-cooled fast reactor;Journal of Nuclear Materials;2017-11

5. Larson–Miller Failure Modeling of Aluminum in Fire;Metallurgical and Materials Transactions A;2010-07-17