Alexander H Murray

US Patent:

6372157, Apr 16, 2002

Filed:

Mar 24, 1997

Appl. No.:

08/826088

Inventors:

Steven M. Mirsky - Greenbelt MD
Alexander P. Murray - Gaithersburg MD

Assignee:

The United States of America as represented by the United States Department of Energy - Washington DC

International Classification:

G21C 724

US Classification:

252478, 2505151

Abstract:

An improved radiation shielding material and storage systems for radioactive materials incorporating the same. The PYRolytic Uranium Compound (âPYRUCâ) 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.

US Patent:

6599490, Jul 29, 2003

Filed:

Apr 15, 2002

Appl. No.:

10/121745

Inventors:

Steven M. Mirsky - Greenbelt MD
Alexander P. Murray - Gaithersburg MD

Assignee:

The United States of America as represented by the United States Department of Energy - Washington DC

International Classification:

C01G 4300

US Classification:

423256, 423 11

Abstract:

An improved radiation shielding material and storage systems for radioactive materials incorporating the same. The PYRolytic Uranium Compound (âPYRUCâ) 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.

US Patent:

6960311, Nov 1, 2005

Filed:

Apr 15, 2002

Appl. No.:

10/121871

Inventors:

Steven M. Mirsky - Greenbelt MD, US
Stephen J. Krill - Arlington VA, US
Alexander P. Murray - Gaithersburg MD, US

Assignee:

The United States of America as represented by the United States Department of Energy - Washington DC

International Classification:

C01G056/00
C04B035/66

US Classification:

252478, 423 11, 423261

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.