Evaluation of the radiation damage parameters of ODS steel alloys in the first wall of deuterium-tritium fusion-fission (hybrid) reactors

2017 ◽  
Vol 42 (1) ◽  
pp. 198-206 ◽  
Author(s):  
Güven Tunç ◽  
Hacı Mehmet Şahin ◽  
Sümer Şahin
Keyword(s):  
Radiation Damage ◽  
First Wall ◽  
Steel Alloys ◽  
Ods Steel ◽  
Hybrid Reactors

Assessment of radiation damage of the first wall of a fusion neutron source DEMO-FNS with a blanket for transmutation of minor actinides

2021 ◽  
Author(s):  
Alexey V. Zhirkin ◽  
V P Budaev ◽  
Alexander O Goltsev ◽  
Alexey V Dedov ◽  
Alexander T Komov ◽  
...  
Keyword(s):  
Radiation Damage ◽  
Neutron Source ◽  
Minor Actinides ◽  
First Wall ◽  
Fusion Neutron ◽  
Fusion Neutron Source

scholarly journals The Sensitivity of the First Wall Radiation Damage to Fusion Reactor Blanket Composition

1978 ◽  
Vol 40 (3) ◽  
pp. 348-451
Author(s):  
J. M. Barnes ◽  
R. T. Santoro ◽  
T. A. Gabriel
Keyword(s):  
Radiation Damage ◽  
Fusion Reactor ◽  
First Wall ◽  
Fusion Reactor Blanket

Temperature Dependence of Radiation Damage in ODS Steel Studied by Triple Beam Irradiation and Positron Annihilation Techniques

2017 ◽  
Vol 373 ◽  
pp. 91-95 ◽  
Author(s):  
Da Qing Yuan ◽  
Qiao Li Zhang ◽  
Ping Fan ◽  
Xian Ping Wang ◽  
Bin Long ◽  
...  
Keyword(s):  
Radiation Damage ◽  
Positron Annihilation ◽  
Ion Beam ◽  
Positron Beam ◽  
Doppler Broadening ◽  
Beam Irradiation ◽  
Single Beam ◽  
Positron Annihilation Lifetime ◽  
Ods Steel ◽  
S Parameter

The oxide dispersed strengthened (ODS) ferritic-martensitic steel was irradiated by 100MeV iron ion whose energy was degraded by using a Ta foil of 4 μm thick, 100 keV Hydrogen and 200 keV Helium at 480, 515, 550 and 580 °C. The irradiation fluences were 1×1016, 1.1×1015 and 6.8×1013/cm2, respectively for Fe, H and He. The techniques of positron annihilation lifetime and Doppler broadening of slow positron beam were utilized to examine the produced radiation damage. At 550 °C the maximal positron annihilation lifetime and S parameter of Doppler broadening were observed, implyin g tha t 550 °C is the pea k temperature of swelling. The S parameter and annihilation lifetime of the sample irradiated at 515 °C by the single Fe ion beam were smaller compared to the triple beam irradiation at the same temperature, implying that the triple beam irradiation caused more severe damage than the single beam irradiation.

scholarly journals MONTE-CARLO STUDIES OF RADIATION DAMAGE INDUCED BY FUSION(I)——α-PARTICLES AT THE FIRST-WALL

1991 ◽  
Vol 40 (8) ◽  
pp. 1236
Author(s):  
HUO YU-KUN ◽  
WU XUAN-HONG ◽  
SHAO QI-YUN ◽  
CHEN JIAN-XIN ◽  
WU SHI-MING ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Radiation Damage ◽  
First Wall ◽  
Monte Carlo Studies ◽  
Α Particles

Radiation Damage in Liquid-Protected First-Wall Materials for IFE-Reactors

1996 ◽  
Vol 30 (3P2A) ◽  
pp. 1027-1035 ◽  
Author(s):  
Sümer Sahin ◽  
Ralph W. Moir ◽  
Abdulmuttalip ŞAHINASLAN ◽  
Haci Mehmet ŞAHIN
Keyword(s):  
Radiation Damage ◽  
First Wall ◽  
Wall Materials

scholarly journals Experimental Investigation of EU-DEMO Breeding Blanket First Wall Mock-Ups in Support of the Manufacturing and Material Development Programmes

Energies ◽  
2021 ◽  
Vol 14 (22) ◽  
pp. 7580
Author(s):  
Bradut-Eugen Ghidersa ◽  
Ali Abou Sena ◽  
Michael Rieth ◽  
Thomas Emmerich ◽  
Martin Lux ◽  
...  
Keyword(s):  
Infrared Camera ◽  
Oxide Dispersion Strengthened ◽  
Functionally Graded ◽  
The Other ◽  
Oxide Dispersion ◽  
First Wall ◽  
Material Development ◽  
Ods Steel ◽  
Steel Layer ◽  
Functionally Graded Layer

This paper presents the testing campaign of the two First Wall mock-ups in the HELOKA facility, one mock-up having a 3 mm thick Oxide Dispersion Strengthened (ODS) steel layer on its surface and the other featuring a tungsten functionally graded cover. Special consideration is given to the diagnostics used for these tests, in particular, the measurement of the surface temperature of the tungsten functionally graded layer with an infrared camera. Additionally, the paper looks into the uncertainty associated with the calorimetric evaluation of the applied heating power for these experiments.

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