Douglas United Nuclear, Inc., sponsored research and development programs, FY-1967 (open access)

Douglas United Nuclear, Inc., sponsored research and development programs, FY-1967

Douglas United Nuclear, Inc., has allocated to the Pacific Northwest Laboratory $542,000 of 02 Research and Development funds and $455,000 of Process Technology funds for FY-1967. Of these, $392,000 of 02 Research and Development funds and $420,000 of Process Technology funds are the responsibility of the Research and Engineering Section. The balance in each case is the responsibility of the Production Fuels Section. Representatives of these Sections have met with Pacific Northwest Laboratory personnel to develop programs to be undertaken in FY-1967. This document briefly summarizes the results of the discussions and delineates the work to be accomplished.
Date: July 12, 1966
Creator: Reid, R. W. & Stringer, J. T.
System: The UNT Digital Library
Status of Special Reactor Process Tube Loadings (open access)

Status of Special Reactor Process Tube Loadings

The pages of the report show the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. For further description of column headings and the current discharge goal exposure plan refer to Document DUN-1048.
Date: July 12, 1966
Creator: Walton, R. P.
System: The UNT Digital Library
Thermal analysis of a SNAP-8 type reactor system during atmospheric reentry. Thermo-physics technical note No. 76 (open access)

Thermal analysis of a SNAP-8 type reactor system during atmospheric reentry. Thermo-physics technical note No. 76

A thermal analysis was carried out to determine the temperature distribution in a SNAP-8 type reactor system during atmopsheric reentry. Of particular interest are the temperature distributions in the reactor upper head, the upper grid plate, and the vessel wall. The time and altitude were determined at which the upper head falls away from the reactor core due to having a portion of its wall melted through. The time and altitude of the melting of the upper grid plate and vessel wall were also determined. The effects of reentry attitude or equivalent angle of attack and initial temperature on the thermal behavior of the system were investigated. The computer programs used in various phases of the analysis were NEWTON (drag coefficient), RESTORE (reentry trajectory), and TAP (thermal model).
Date: July 12, 1966
Creator: Montgomery, L. D. & Mouradian, E. M.
System: The UNT Digital Library