SANS and TEM of ferritic–martensitic steel T91 irradiated in FFTF up to 184dpa at 413°C-Reference-Cited by-同舟云学术

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SANS and TEM of ferritic–martensitic steel T91 irradiated in FFTF up to 184dpa at 413°C

Published:2013-09 Issue:1-3 Volume:440 Page:91-97
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Van den Bosch J.,Anderoglu O.,Dickerson R.,Hartl M.,Dickerson P.,Aguiar J.A.,Hosemann P.,Toloczko M.B.,Maloy S.A.

Publisher

Elsevier BV

Subject

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

Reference24 articles.

1. Sodium fast reactor evaluation: Core materials

2. Nuclear Materials Part I, Materials Science and Technology;Garner,1994

3. Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure

4. Status of liquid metal cooled fast reactor technology, IAEA-TECDOC-1083, IAEA, 1999.

5. Influence of high dose neutron irradiation on microstructure of EP-450 ferritic–martensitic steel irradiated in three Russian fast reactors

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