Published December 1983 | Version v1
Report Restricted

Fuel systems for compact fast space reactors

Description

About 200 refractory metal clad ceramic fuel pins have been irradiated in thermal reactors under the 1200 K to 1550 K cladding temperature conditions of primary relevance to space reactors. This paper reviews performance with respect to fissile atom density, operating temperatures, fuel swelling, fission gas release, fuel-cladding compatibility, and consequences of failure. It was concluded that UO2 and UN fuels show approximately equal performance potential and that UC fuel has lesser potential. W/Re alloys have performed quite well as cladding materials, and Ta, Nb, and Mo/Re alloys, in conjunction with W diffusion barriers, show good promise. Significant issues to be addressed in the future include high burnup swelling of UN, effects of UO2-Li coolant reaction in the event of fuel pin failure, and development of an irradiation performance data base with prototypically configured fuel pins irradiated in a fast neutron flux

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE84006545.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
23 p.
Report number
HEDL-SA--3065-FP

Conference

Title
Symposium on space nuclear power systems.
Dates
10-13 Jan 1984.
Place
Albuquerque, NM (USA).

Optional Information

Secondary number(s)
CONF-840113--6.