A computationally simple model for determining the time dependent spectral neutron flux in a nuclear reactor core

Journal of Nuclear Materials

Volumn 357, Issue 1-3, 2006, Pages 19-30

  Schneider, E A ^a   Deinert, M R ^b   Cady, K B ^b  

^a The University of Texas at Austin   (United States)

^b Department of Obstetrics Gynecology   (United States)

Author keywords

A0200; F0700; M0200; N0500; P0700; U0200

Indexed keywords

COMPUTER SIMULATION; COMPUTER SOFTWARE; COOLANTS; MODERATORS; SPECTRUM ANALYSIS; TIME VARYING SYSTEMS;

COLLISION PROBABILITY; MODERATOR GEOMETRY; NEUTRON FLUX; NEUTRON TRANSPORT;

REACTOR CORES;

EID: 33749264389     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2006.04.012     Document Type: Article

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