Burnup dependent neutron flux and heat source distribution in sphere-pac mixed carbide fuels
By: by Cheryl A. Robinson.
Published: 1981
Language: eng
Number of pages: 59
Subjects: Neutron flux.; Nuclear fuels.; Nuclear engineering -- Mathematical models.
Notes: Typescript (photocopy).

Thesis (M.S.)--Oregon State University, 1982.

Bibliography: leaf 46.