Damage structural behaviour by electron irradiation of MnCr austenitic stainless steels

1985 ◽  
Vol 133-134 ◽  
pp. 566-570 ◽  
Author(s):  
H. Takahashi ◽  
T. Takeyama ◽  
K. Tanikawa ◽  
R. Miura
Keyword(s):  
Electron Irradiation ◽  
Stainless Steels ◽  
Austenitic Stainless Steels ◽  
Structural Behaviour

Electron irradiation damage in austenitic stainless steels

1991 ◽  
Vol 179-181 ◽  
pp. 526-528 ◽  
Author(s):  
Jiguang Sun ◽  
Jiapu Qian ◽  
Zhuoyong Zhao ◽  
Jiming Chen ◽  
Zengyu Xu
Keyword(s):  
Electron Irradiation ◽  
Stainless Steels ◽  
Austenitic Stainless Steels ◽  
Irradiation Damage

scholarly journals A positron annihilation study of defect accumulation in phosphorus- and titanium-alloyed austenitic stainless steels under electron irradiation at room temperature

2020 ◽  
pp. 27-34
Author(s):  
D. A. Perminov ◽  
Keyword(s):  
Positron Annihilation ◽  
Electron Irradiation ◽  
Stainless Steels ◽  
Room Temperature ◽  
Austenitic Stainless Steels ◽  
Positron Annihilation Spectroscopy ◽  
High Concentration ◽  
Noticeable Effect ◽  
Vacancy Defects ◽  
Positron Annihilation Study

The effect of phosphorus and titanium additions on the accumulation of vacancy defects in Cr16Ni15Mo3 austenitic stainless steels under electron irradiation at room temperature is studied by positron annihilation spectroscopy. It is shown that, at this temperature, phosphorus has no noticeable effect on the accumulation of vacancy defects. This is due to the low mobility of vacancies and the low concentration of impurities. Titanium, due to its high concentration, enhances the accumulation of vacancy defects during irradiation, but this effect is weak.

Grain boundary migration during electron irradiation in austenitic stainless steels

1985 ◽  
Vol 133-134 ◽  
pp. 575-579 ◽  
Author(s):  
Kiyotomo Nakata ◽  
Yoshio Katano ◽  
Isao Masaoka ◽  
Kensuke Shiraishi
Keyword(s):  
Grain Boundary ◽  
Electron Irradiation ◽  
Stainless Steels ◽  
Boundary Migration ◽  
Austenitic Stainless Steels ◽  
Grain Boundary Migration

Radiation Damage Studies with the HVEM

1972 ◽  
Vol 30 ◽  
pp. 680-681
Author(s):  
J. J. Laidler ◽  
B. Mastel
Keyword(s):  
Radiation Damage ◽  
Stainless Steels ◽  
Volume Expansion ◽  
Austenitic Stainless Steels ◽  
Test Facility ◽  
Fast Breeder Reactors ◽  
Breeder Reactors ◽  
Under Construction ◽  
Development Laboratory ◽  
Insight Into

One of the major materials problems encountered in the development of fast breeder reactors for commercial power generation is the phenomenon of swelling in core structural components and fuel cladding. This volume expansion, which is due to the retention of lattice vacancies by agglomeration into large polyhedral clusters (voids), may amount to ten percent or greater at goal fluences in some austenitic stainless steels. From a design standpoint, this is an undesirable situation, and it is necessary to obtain experimental confirmation that such excessive volume expansion will not occur in materials selected for core applications in the Fast Flux Test Facility, the prototypic LMFBR now under construction at the Hanford Engineering Development Laboratory (HEDL). The HEDL JEM-1000 1 MeV electron microscope is being used to provide an insight into trends of radiation damage accumulation in stainless steels, since it is possible to produce atom displacements at an accelerated rate with 1 MeV electrons, while the specimen is under continuous observation.

Sign in / Sign up

Export Citation Format

Share Document