Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Materials requirements for liquid metal fast breeder reactors

Journal Article · · Metall. Trans., A; (United States)
DOI:https://doi.org/10.1007/BF02646695· OSTI ID:6516285
Materials requirements for Liquid Metal Fast Breeder Reactors (LMFBRs) are quite varied with requisite applications ranging from ex-reactor components such as piping, pumps, steam generators and heat exchangers to in-reactor components such as heavy section reactor vessels, core structurals, fuel pin cladding and subassembly flow ducts. Requirements for ex-reactor component materials include: good high temperature tensile, creep and fatigue properties; compatibility with high temperature flowing sodium; resistance to wear, stress corrosion cracking, and crack propagation; and good weldability. Requirements for in-reactor components include most of those cited above for ex-reactor components as supplemented by the following: resistance to radiation embrittlement, swelling and radiation enhanced creep; good neutronics; compatibility with fuel and fission product materials; and resistance to mass transfer via flowing sodium. Extensive programs are currently in place in a number of national laboratories and industrial contractors to address the materials requirements for LMFBRs. These programs are focused on meeting the near term requirements of early LMFBRs such as the Fast Flux Test Facility and the Clinch River Breeder Reactor as well as the longer term requirements of larger near-commercial and fully-commercial reactors.
Research Organization:
Energy Research and Development Administration, Washington, DC
OSTI ID:
6516285
Journal Information:
Metall. Trans., A; (United States), Journal Name: Metall. Trans., A; (United States) Vol. 9:2; ISSN MTTAB
Country of Publication:
United States
Language:
English

Similar Records

A manufacturer's view of the US breeder program
Conference · Tue Jun 01 00:00:00 EDT 1982 · Energy Technol. (Wash., D.C.); (United States) · OSTI ID:5244472

Experimental breeder reactor-II: 20 yr of operating experience
Journal Article · · Nucl. Saf.; (United States) · OSTI ID:6815317

Sodium flow blockage in liquid-metal fast breeder reactors: sweepout of a planar blockage
Journal Article · Sun Nov 30 23:00:00 EST 1980 · Nucl. Sci. Eng.; (United States) · OSTI ID:6883831