skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Impact of fuel fabrication and fuel management technologies on uranium utilization

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:182102
;  [1]
  1. Westinghouse Electric Corporation, Pittsburgh, PA (United States)

Uranium utilization in commercial pressurized water reactors is a complex function of original NSSS design, utility energy requirements, fuel assembly design, fuel fabrication materials and fuel management optimization. Fuel design and fabrication technologies have reacted to the resulting market forcing functions with a combination of design and material changes. The technologies employed have included ever-increasing fuel discharge burnup, non-parasitic structural materials, burnable absorbers, and fissile material core zoning schemes (both in the axial and radial direction). The result of these technological advances has improved uranium utilization by roughly sixty percent from the infancy days of nuclear power to present fuel management. Fuel management optimization technologies have also been developed in recent years which provide fuel utilization improvements due to core loading pattern optimization. This paper describes the development and impact of technology advances upon uranium utilization in modem pressurized water reactors.

OSTI ID:
182102
Report Number(s):
CONF-940501-; ISSN 0003-018X; TRN: 95:004487-0130
Journal Information:
Transactions of the American Nuclear Society, Vol. 70, Issue Suppl.1; Conference: 9. Pacific basin nuclear conference, Sydney (Australia), 1-5 May 1994; Other Information: PBD: 1994
Country of Publication:
United States
Language:
English

Similar Records

Nuclear Fuel Management Optimization: A Work in Progress
Journal Article · Fri Jul 15 00:00:00 EDT 2005 · Nuclear Technology · OSTI ID:182102

Pushing nuclear fuel toward extended burnup
Journal Article · Thu Mar 01 00:00:00 EST 1984 · Power; (United States) · OSTI ID:182102

Experience in PWR and BWR mixed-oxide fuel management
Journal Article · Thu Apr 01 00:00:00 EST 1993 · Nuclear Technology; (United States) · OSTI ID:182102