Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: April-June 1961 (open access)

Maritime Gas-Cooled Reactor Program, Quarterly Progress Report: April-June 1961

Quarterly report discussing activities of the Maritime Gas-Cooled Reactor (MGCR) Program and the progress of the Program in developing a nuclear-powered marine propulsion system utilizing a high-temperature, gas-cooled nuclear reactor, close-cycle gas-turbine power plant.
Date: July 31, 1963
Creator: unknown
System: The UNT Digital Library
Maritime Gas-Cooled Reactor Program: Suggested Values for the Partial Cross Sections of U²³⁵ for Use in the Neutronic Analysis of Thermal and Intermediate Reactors (open access)

Maritime Gas-Cooled Reactor Program: Suggested Values for the Partial Cross Sections of U²³⁵ for Use in the Neutronic Analysis of Thermal and Intermediate Reactors

From abstract: In this report a consistent set of U-235 partial cross sections for use in the analysis of thermal or intermediate reactor systems has been provided.
Date: July 17, 1961
Creator: Goodjohn, A. J. & Wikner, N. F.
System: The UNT Digital Library