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This work is licensed under a Creative Commons Attribution-NonCommercial 4.0 International License
Article
A Monte Carlo Simulation of Radiation Damage of SiC and Nb Using JA-IPU Code
Author(s)
Nagendra Singh Raghaw2, Vinod Kumar1, Ambika Tundwal1, Yury Korovin3 and Jindrich Adam4
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DOI:10.17265/1934-8975/2015.11.005
Affiliation(s)
1. University School of Basic and Applied Sciences, GGS Indraprastha University, New Delhi 110078, India
2. HENPL (High Energy Nuclear Physics Laboratory) (ADS Program), University of Rajasthan, Jaipur 302004, India
3. INPE (Institute for Nuclear Power Engineering), Kaluga Region, Obninsk 249020, Russia
4. Laboratory for Nuclear Problem, Joint Institute of Nuclear Research, Dubna 141980, Russia
ABSTRACT
MC (Monte Carlo) simulation code, JA-IPU
is used to study radiation damage of SiC irradiated to spallation neutron and AmBe
neutron spectra. The code is based on
the major physical processes of radiation damage on incorporation of atomic collision
cascade and limited to 10 MeV neutron energy. A phenomenological relation for radiation
swelling is also derived. Based on the calculation of swelling, DPA (displacement
per atom), defect production efficiency and effective threshold energy, Edeff from the data of MC
simulation, SiC is inferred to be a highly radiation resistant material when compared
with Nb and Ni metals which are used in composition of several reactor steels. Experimental
results of hill-hock density measured using AFM (atomic force microscopy), also confirm radiation
resistant behavior of SiC.
KEYWORDS
Monte-Carlo simulation, radiation resistant material, DPA, effective damage threshold energy.
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