Creep behavior of reduced activation ferritic/martensitic steels irradiated at 573 and 773K up to 5dpa-Reference-Cited by-同舟云学术

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Creep behavior of reduced activation ferritic/martensitic steels irradiated at 573 and 773K up to 5dpa

Published:2007-08 Issue: Volume:367-370 Page:122-126
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Ando M.,Li M.,Tanigawa H.,Grossbeck M.L.,Kim S.,Sawai T.,Shiba K.,Kohno Y.,Kohyama A.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference12 articles.

1. The response of austenitic steels to radiation damage

2. The in-reactor deformation of the PCA alloy

3. Irradiation creep in type 316 stainless steel and us PCA with fusion reactor He/dpa levels

4. Irradiation creep and swelling of the fusion heats of PCA, HT9 and 9Cr-1Mo irradiated to high neutron fluence

5. Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr-1Mo to 208 dpa at ~ 400°C

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1. Establishing machine-learning approach for predicting outer-diametral strains in ferritic/martensitic (F/M) steel tubes during in-reactor neutron-irradiation creep experiments;Progress in Nuclear Energy;2024-12

2. Tensile and creep properties of small specimens of reduced-activation ferritic steel F82H, and the correlation to standard specimen data;Nuclear Science and Technology Open Research;2024-07-26

3. Development of reduced-activation and radiation-resistant high-entropy alloys for fusion reactor;International Journal of Refractory Metals and Hard Materials;2024-06

4. Thermal creep analysis and correlation development for manufactured HT9 cladding;Journal of Nuclear Materials;2024-05

5. Assessment of thermal and radiation induced creep in the dual cooled lead lithium blanket;Fusion Engineering and Design;2024-04

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