THE WCAP-1 AND 2 CAPSULE IRRADIATION PROGRAM INTERIM REPORT

Technical Report · Tue Sep 01 04:00:00 EDT 1959

OSTI ID:4189324

Duncan, R; Jedruch, J; King, R

In-pile capsules contrining UO/sub 2/ enriched to 2.7 to 5.4% U/sup 235/ with pellet-to-tube diametrical clearances of 0.000 to 0.005 in. were fabricated. Thirteen were placed in the Matarials Testing Reactor and five in the Engineering Test Beactor to verify the performance of the Yankee fuel element design under irradiation. Stainless steel (types 504 and 516) cladding exhibited successful performance when exposed to representative fuel burnups under Yankee power ratings. Satisfactory performance of ferrule brazed joints used in irradiation specimen fuel assemblies was determined. In-pile test results indicated that under Yankee irradiation conditions no diametrical dimensional changes of fuel rods greater than 0.0005 inches may be expected. The radial cracking exhibited by uranium oxide pellets produced no apparent effect on pellet fuel performance at the power ratings evaluated. Experimental volumes of fission gases released were considerably lower than theoretical predictions. The above results were determined from tests on 7 of the 18 irradiated in-pile capsules. (C.J.G.)

• Research Organization: Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
• NSA Number: NSA-14-014133
• OSTI ID: 4189324
• Report Number(s): YAEC-158
• Country of Publication: United States
• Language: English

Related Subjects

BRAZING
BURNUP
CONFIGURATION
CRACKS
EXPANSION
FISSION PRODUCTS
FUEL CANS
FUEL ELEMENTS
GASES
IN PILE LOOPS
IRRADIATION
JOINTS
MATERIALS TESTING
METALS, CERAMICS, AND OTHER MATERIALS
PELLETS
PERFORMANCE
RADIATION EFFECTS
REACTORS
RODS
STAINLESS STEELS
TUBES
URANIUM DIOXIDE
VOLUME