DocumentCode
2342657
Title
Generation of thermal neutron scattering libraries for beryllium carbide
Author
Hehr, Brian D. ; Hawari, Ayman I.
Author_Institution
Dept. of Nucl. Eng., North Carolina State Univ., Raleigh, NC, USA
fYear
2010
fDate
21-24 March 2010
Firstpage
1
Lastpage
5
Abstract
Beryllium carbide is under investigation as a possible structural or moderator material in fission and fusion systems. While many of the physical properties of beryllium carbide have already been studied, neutronic properties such as the thermal scattering cross-section are not well known. The purpose of this work is to evaluate the scattering cross section of beryllium carbide through quantum mechanical ab-initio simulations. In benchmarking the calculation, physical properties such as the lattice parameter and heat capacity are also computed and compared against measured data.
Keywords
ab initio calculations; beryllium compounds; fission reactor fuel; fusion reactor blankets; neutron diffusion; BeC; beryllium carbide; fission reactor fuel; fission system; fusion reactor blanket material; fusion system; moderator material; neutronic properties; quantum mechanical ab-initio simulations; structural material; thermal neutron scattering libraries; thermal scattering cross-section; Atomic measurements; Computational modeling; Electrons; Lattices; Libraries; Light scattering; Neutron spin echo; Particle scattering; Phonons; Renewable energy resources;
fLanguage
English
Publisher
ieee
Conference_Titel
Nuclear & Renewable Energy Conference (INREC), 2010 1st International
Conference_Location
Amman
Print_ISBN
978-1-4244-5213-2
Electronic_ISBN
978-1-4244-5214-9
Type
conf
DOI
10.1109/INREC.2010.5462583
Filename
5462583
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