Open AccessSome Calculations for a Plutonium-Fueled ZPR-III
Author(s) -
A.R. Baker
Publication year - 1960
Language(s) - English
Resource type - Reports
DOI - 10.2172/4142102
Subject(s) - plutonium , reactivity (psychology) , blanket , delayed neutron , neutron transport , control rod , prompt neutron , mockup , neutron , nuclear engineering , materials science , chemistry , radiochemistry , nuclear physics , neutron temperature , physics , engineering , composite material , medicine , alternative medicine , pathology
Calculations of critical size, reactivity coefficients, and delayed neutron fractions are described for mockups of a plutonium-fueled EBR-I (Mark IV) and five possible metal-fueled power reactors. The calculations for critical size were performed using the SNG transport-theory code. The reactivity coefficients were estimated by SNG calculations or by one-group perturbation- theory desk calculations. The delayed-neutron fractions were estimated by an approximate method, which starts with a calculation of beta for a bare core and then makes a correction for the small effect of the blanket. The reactivity effects studied were the effects of fuel-plate and whole-core expansion and control-rod worths. (auth