Optimizing a three-element core design for the Advanced Neutron Source Reactor [electronic resource].

Published: Washington, D.C. : United States. Dept. of Energy, 1995.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description: 8 pages : digital, PDF file
Additional Creators: Oak Ridge National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information

Access Online

www.osti.gov

Availability

Finding items...

Restrictions on Access

Free-to-read Unrestricted online access

Summary

Source of neutrons in the proposed Advanced Neutron Source facility is a multipurpose research reactor providing 5-10 times the flux, for neutron beams, of the best existing facilities. Baseline design for the reactor core, based on the ``no new inventions`` rule, was an assembly of two annular fuel elements similar to those used in the Oak Ridge and Grenoble high flux reactors, containing highly enriched U silicide particles. DOE commissioned a study of the use of medium- or low-enriched U; a three-element core design was studied as a means to provide extra volume to accommodate the additional U compound required when the fissionable ²³⁵U has to be diluted with ²³⁸U to reduce the enrichment. This paper describes the design and optimization of that three-element core.

Report Numbers

E 1.99:conf-950601--29
conf-950601--29

Subject(s)

Nuclear Reactor Technology

Other Subject(s)

Note

Published through SciTech Connect.
12/31/1995.
"conf-950601--29"
"DE96008581"
Annual meeting of the American Nuclear Society (ANS), Philadelphia, PA (United States), 25-29 Jun 1995.
West, C.D.

Funding Information

AC05-84OR21400

View MARC record | catkey: 14363240