Abstract: A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield.
Type:
Grant
Filed:
September 10, 1952
Date of Patent:
August 17, 1976
Assignee:
The United States of America as represented by the United States Energy Research and Development Administration
Abstract: 1. The method of operating a water-cooled neutronic reactor having a graphite moderator which comprises flowing a gaseous mixture of carbon dioxide and helium, in which the helium comprises 40-60 volume percent of the mixture, in contact with the graphite moderator.
Type:
Grant
Filed:
June 19, 1952
Date of Patent:
July 27, 1976
Assignee:
The United States of America as represented by the United States Energy Research and Development Administration