Search PubMed⌕ Search

Biomedical subjects

J C Courtney

Publications and source records attributed to J C Courtney.

5 recordsLinked to original sources
PubMed1992

Photon shielding for 241Am surface and point sources.

To determine radiation protection requirements for work with actinide elements, a method for rapidly estimating effective dose-equivalent rates from low-energy photons has been developed. This paper describes results obtained from a personal computer program that incorporates the point kernel technique to predict radiation fields from shielded and unshielded sources containing 241Am. Information generated has been used to determine procedures and to design facilities for handling actinides at Argonne National Laboratory's site at the Idaho National Engineering Laboratory. Area or point sources can be treated; effects of Compton scattering in air and in solid shields are considered. Users can select an appropriate response function; their choice has a strong influence on predicted dose rates from unshielded sources.

Americium↗
PubMed1991

A description of the demonstration Integral Fast Reactor fuel cycle facility.

A fuel examination facility at the Idaho National Engineering Laboratory is being converted into a facility that will electrochemically process spent fuel. This is an important step in the demonstration of the Integral Fast Reactor concept being developed by Argonne National Laboratory. Renovations are designed to bring the facility up to current health and safety and environmental standards and to support its new mission. Improvements include the addition of high-reliability earthquake hardened off-gas and electrical power systems, the upgrading of radiological instrumentation, and the incorporation of advances in contamination control. A major task is the construction of a new equipment repair and decontamination facility in the basement of the building to support operations.

Facility Design and Construction↗
PubMed1991

Radiation shielding design for a hot repair facility.

A new repair and decontamination area is being built to support operations at the demonstration fuel cycle facility for the Integral Fast Reactor program at Argonne National Laboratory's site at the Idaho National Engineering Laboratory. Provisions are made for remote, glove wall, and contact maintenance on equipment removed from hot cells where spent fuel will be electrochemically processed and recycled to the Experimental Breeder Reactor-II. The source for the shielding design is contamination from a mix of fission and activation products present on items removed from the hot cells. The repair facility also serves as a transfer path for radioactive waste produced by processing operations. Radiation shields are designed to limit dose rates to no more than 5 microSv h-1 (0.5 mrem h-1) in normally occupied areas. Point kernel calculations with buildup factors have been used to design the shielding and to position radiation monitors within the area.

Facility Design and Construction↗