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MCNP 4A computer code for criticality, neutron flux and spectrum calculations on the reactor VR-1
MCNP 4A computer code for criticality, neutron flux and spectrum calculations on the reactor VR-1
1996
L. Sklenka
A. Kolros
Keywords:
Nuclear physics
Source code
neutron spectra
Neutron flux
Spectral line
Radiation flux
Spectrum (functional analysis)
Physics
Criticality
Correction
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