Accession Number:

AD0602160

Title:

NEUTRON DOSIMETRY SAMPLING OF THE OMRE PRESSURE VESSEL AND GRID PLATES

Descriptive Note:

Final rept.

Corporate Author:

NAVAL RESEARCH LAB WASHINGTON DC

Report Date:

1964-06-02

Pagination or Media Count:

23.0

Abstract:

Upon the shutdown of the organic moderated reactor experiment OMRE at the National Reactor Testing Station in Idaho, a program was initiated to determine the total neutron dosage and radiation induced transition temperature increase to the pressure vessel and upper grid plates. Drillings were made across the grid plate and the chips were collected from each position to determine the cross-plate neutron exposure gradient. Drillings were taken and collected from the pressure vessel at the fuel centerline, upper and lower grid plate regions, and mid-way between, to determine the vertical neutron flux gradient. The results of the neutron dose analysis of these components are presented. Based upon the results, recommendations are made for testing of the material to determine the transition temperature increase.

Subject Categories:

  • Nuclear Instrumentation

Distribution Statement:

APPROVED FOR PUBLIC RELEASE