Comparisons with experiment of calculated dimensional changes and failure analysis of irradiated bulk oxide fuel test rods using the CYGRO-1 computer program (LWBR Development Program)

Technical Report · Thu Sep 01 04:00:00 EDT 1966

OSTI ID:6741694

Duncombe, E; Meyer, J E; Coffman, W A

Analysis techniques were developed and incorporated into a digital computer program (CYGRO-1) to estimate the temperature, stresses, deformation, and failure characteristics of bulk-oxide nuclear reactor fuel rods during life. Comparisons are made between CYGRO calculations and results from irradiation tests of a series of Zircaloy bulk-oxide rods. Methods of incorporating material property information for a variety of physical processes which occur in the fuel are presented in detail. (NSA 21: 1963)

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• DOE Contract Number: AT(11-1)-GEN-14
• OSTI ID: 6741694
• Report Number(s): WAPD-TM-583
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
ACCIDENTS
BREEDER REACTORS
C CODES
COMPUTER CODES
DEFORMATION
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
LWBR TYPE REACTORS
RADIATION EFFECTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
STRESSES
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS