Some Macroscopic Characteristics of Fast Reactor Cores of Intermediate Capacity

7/14/2012 2012 - #03 Physics and technology of nuclear reactors

Khorasanov G.L. Blokhin A.I.

https://doi.org/10.26583/npe.2012.3.02

Mean neutron energies, one-group cross sections of neutron capture by uranium-238 and fission of americium-241 for the Russian reactors BN-600, BREST-300 and RBEC-340 (RBEC-M) are calculated using MCNP5 code. For RBEC-340 these characteristics are calculated for the reactor with its standard lead-bismuth coolant as well as for this reactor cooled with Pb-208, as it was proposed by the authors of the paper.

Link for citing the article: Khorasanov G.L., Blokhin A.I. Some Macroscopic Characteristics of Fast Reactor Cores of Intermediate Capacity. Izvestiya vuzov. Yadernaya Energetika. 2012, no. 3, pp. 18-22; DOI: https://doi.org/10.26583/npe.2012.3.02 (in Russian).