Turbulent coaxial flow analysis for predicting fuel mass in reactor cavity
Estimates of fuel containment in a coaxial flow gas-core nuclear rocket
ANN. MEETING OF THE AM. NUCL. SOC. ; 1970 ; LOS ANGELES
01.01.1970
Report
Keine Angabe
Englisch
Estimates of fuel containment in a coaxial flow gas-core nuclear rocket
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