NEUTRON DOSIMETRY SAMPLING OF THE OMRE PRESSURE VESSEL AND GRID PLATES

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...

Full description

Saved in:
Bibliographic Details
Main Authors: Serpan, Jr , Charles Z, Steele, Lendell E
Format: Report
Language:English
Subjects:
DAMAGE
MECHANICAL PROPERTIES
NEUTRON ABSORPTION
NEUTRON COUNTERS
NEUTRON EMBRITTLEMENT
NEUTRON FLUX
Nuclear Instrumentation
ORGANIC MODERATED REACTORS
PRESSURE VESSELS
RADIATION EFFECTS
REACTOR MATERIALS
REACTOR SYSTEM COMPONENTS
TRANSITION TEMPERATURE
Online Access:Request full text
Tags: Add Tag
No Tags, Be the first to tag this record!
Description
Summary: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.