Radiation shielding materials and containers incorporating same
Abstract
An improved radiation shielding material and storage systems for radioactive materials incorporating the same. The PYRolytic Uranium Compound ("PYRUC") shielding material is preferably formed by heat and/or pressure treatment of a precursor material comprising microspheres of a uranium compound, such as uranium dioxide or uranium carbide, and a suitable binder. The PYRUC shielding material provides improved radiation shielding, thermal characteristic, cost and ease of use in comparison with other shielding materials. The shielding material can be used to form containment systems, container vessels, shielding structures, and containment storage areas, all of which can be used to house radioactive waste. The preferred shielding system is in the form of a container for storage, transportation, and disposal of radioactive waste. In addition, improved methods for preparing uranium dioxide and uranium carbide microspheres for use in the radiation shielding materials are also provided.
- Inventors:
-
- Greenbelt, MD
- Arlington, VA
- Gaithersburg, MD
- Issue Date:
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 920032
- Patent Number(s):
- 6960311
- Assignee:
- The United States of America as represented by the United States Department of Energy (Washington, DC)
- Patent Classifications (CPCs):
-
C - CHEMISTRY C01 - INORGANIC CHEMISTRY C01B - NON-METALLIC ELEMENTS
G - PHYSICS G21 - NUCLEAR PHYSICS G21F - PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
Citation Formats
Mirsky, Steven M, Krill, Stephen J, and Murray, Alexander P. Radiation shielding materials and containers incorporating same. United States: N. p., 2005.
Web.
Mirsky, Steven M, Krill, Stephen J, & Murray, Alexander P. Radiation shielding materials and containers incorporating same. United States.
Mirsky, Steven M, Krill, Stephen J, and Murray, Alexander P. Tue .
"Radiation shielding materials and containers incorporating same". United States. https://www.osti.gov/servlets/purl/920032.
@article{osti_920032,
title = {Radiation shielding materials and containers incorporating same},
author = {Mirsky, Steven M and Krill, Stephen J and Murray, Alexander P},
abstractNote = {An improved radiation shielding material and storage systems for radioactive materials incorporating the same. The PYRolytic Uranium Compound ("PYRUC") shielding material is preferably formed by heat and/or pressure treatment of a precursor material comprising microspheres of a uranium compound, such as uranium dioxide or uranium carbide, and a suitable binder. The PYRUC shielding material provides improved radiation shielding, thermal characteristic, cost and ease of use in comparison with other shielding materials. The shielding material can be used to form containment systems, container vessels, shielding structures, and containment storage areas, all of which can be used to house radioactive waste. The preferred shielding system is in the form of a container for storage, transportation, and disposal of radioactive waste. In addition, improved methods for preparing uranium dioxide and uranium carbide microspheres for use in the radiation shielding materials are also provided.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Nov 01 00:00:00 EST 2005},
month = {Tue Nov 01 00:00:00 EST 2005}
}