Title of article :
Nuclear analysis of the copper alloys for fusion technologies by Monte Carlo method
Author/Authors :
Farkas، نويسنده , , G. and Domonko?، نويسنده , , P. and Sluge?، نويسنده , , V. and Ballo، نويسنده , , P.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2006
Pages :
4
From page :
121
To page :
124
Abstract :
The work is focused on the neutronic calculation of the nuclear parameters (distribution of neutron fluency, atomic displacement, nuclear heating, gas production, photon production, nuclear reactions and induced activity) in a specimen of the cooper alloy (CuCrZr) using Monte Carlo Neutron-Particle Transport code MCNP-4C2. This alloy is currently one of the best candidate materials for the first wall of the International Thermonuclear Experimental Reactor (ITER) which will be exposed to high neutron load with energy of about 14.1 MeV. The MCNP model of the investigated specimen (12 × 12 × 0.5 mm) consists of 98.683% Cu, 0.754% Cr, 0.163% Zr and 0.4% Cs. The number of primary knock-out atoms calculated for this alloy specimen is 8.253E−02 atoms/(source neutron cm3). The calculated helium production is 2.857E−03 atoms/(source neutron cm3), and the hydrogen production is 1.387E−02 atoms/(source neutron cm3). Activity of the specimen by copper activation is of about 5 MBq. The TRIM 98.01 code has been used for the simulation of defects creation in copper by hydrogen H+ of 95 keV energy, only. The defects production has been identified in the region of about 400–800 nm. Results obtained by Monte Carlo calculations will be used for understanding of the experimental data from positron annihilation spectroscopy measurements which are scheduled for next year.
Keywords :
MCNP code , Defect production , Monte Carlo simulation , Neutronic calculation , Positron annihilation spectroscopy , Neutron irradiation
Journal title :
Computational Materials Science
Serial Year :
2006
Journal title :
Computational Materials Science
Record number :
1681535
Link To Document :
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