Impact behavior of reduced-activation steels irradiated to 24 dpa

نویسندگان
چکیده

برای دانلود باید عضویت طلایی داشته باشید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Compatibility of Reduced Activation Ferritic/Martensitic Steels with Liquid Breeders

The compatibility of Reduced Activation Ferritic/Martensitic Steel (RAFM) with liquid Li and molten-salt Flibe have been characterized and accessed. Static compatibility tests were carried out in which the specimens were immersed into liquid Li or Flibe in isothermal autoclaves. Also carried out were compatibility tests in flowing liquid Li by thermal convection loops. In the case of liquid Li,...

متن کامل

FTP1/01 Dynamic Mechanical Properties of Reduced Activation Ferritic Steels

A fatigue test method by a miniaturized hourglass-shaped fatigue specimen has been developed for International Fusion Materials Irradiation Facility (IFMIF) and sufficient potential as the alternative to a conventional large specimen was presented. Furthermore, focused ion beam micro-sampling method was successfully applied to microstructural analysis on fracture process. Where, the effects of ...

متن کامل

Neural Network Analysis of Charpy Transition Temperature of Irradiated Low - activation Martensitic Steels

We have constructed a Bayesian neural network model that predicts the change, due to neutron irradiation, of the Charpy ductile-brittle transition temperature (ΔDBTT) of low activation martensitic steels given a 40-dimensional set of data from the literature. The irradiation doses were < 100 displacements per atom (dpa). Results show the high significance of irradiation temperature and (dpa) in...

متن کامل

High Temperature Behavior of Dual Phase Steels

Dual phase steels with different martensite volume fraction and morphology were tensile tested at a temperature range of 25 to 5500C. Stress-strain curves of all steels showed serration flow at temperatures of 250 and 3500C, and smooth flow at the other temperatures. Both yield and ultimate tensile strengths increased with increasing testing temperature up to about 450<sup...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

ژورنال

عنوان ژورنال: Journal of Nuclear Materials

سال: 1996

ISSN: 0022-3115

DOI: 10.1016/0022-3115(95)00173-5