Mechanical behavior of reduced-activation and conventional martensitic steels after neutron irradiation in the range 250-450°C

被引：33
作者：
Alamo, A [1 ]
Horsten, M
Averty, X
Materna-Morris, EI
Rieth, M
Brachet, JC
机构：
[1] CEA Saclay, SRMA, F-91191 Gif Sur Yvette, France
[2] NRG, NL-1755 ZG Petten, Netherlands
[3] CEA Saclay, DMT, SEMI, F-91191 Gif Sur Yvette, France
[4] Forschungszentrum Karlsruhe, Inst Mat Forsch, D-76021 Karlsruhe, Germany
来源：
JOURNAL OF NUCLEAR MATERIALS | 2000年 / 283卷 / PART I期
关键词：
D O I：
10.1016/S0022-3115(00)00076-3
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The objective of this work is to examine the susceptibility to hardening and embrittlement of Fe7.5/11CrWTaV reduced-activation (RA) and conventional 9/12Cr-Mo martensitic steels as a function of fluence up to 10 dpa and irradiation temperature in the range of 250-450 degreesC. For this purpose, materials were irradiated in the Osiris Reactor (Saclay) at 325 degreesC for Various doses ranging from 0.8 dpa to a maximum dose of 8-9 dpa. Available data concern the evolution of tensile properties for doses from 0.8 to 3.4 dpa. On the other hand, RA-steels were irradiated as Charpy V and tensile specimens in the high flux reactor (HFR) at Petten at temperatures ranging from 250 degreesC to 450 degreesC with a dose of about 2.4 dpa. (C) 2000 Elsevier Science B.V. All rights reserved.
引用
收藏
页码：353 / 357
页数：5
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