Irradiation performance of duplex-fuel-pellet test rods depleted to 9 x 10/sup 20/ fissions/cm/sup 3/ of compartment: D-1 test (AWBA development program)

Technical Report · Fri Jan 01 04:00:00 EST 1982

OSTI ID:6887014

Sphar, C D; Mertz, D A; Roesener, W S

This report evaluates the irradiation performance of the D-1 test. The D-1 test is a screening test of the duplex pellet prebreeder reactor fuel concept consisting of a cylindrical thoria pellet surrounded by an annulus containing urania enriched in uranium-235. The duplex pellet geometry offers the advantage of lower fuel temperatures than solid pellets for equal power output and provides a means of including the fertile material in the fuel rods with little or no loss of heat transfer surface while also providing a practical (chemical) means for separating the uranium-233 bred in the thoria central core without contamination by other uranium isotopes in the annulus. The design of the test, which includes duplex pellet annuli of four different compositions (UO/sub 2/, ZrO/sub 2/-UO/sub 2/, ZrO/sub 2/-UO/sub 2/-CaO and ThO/sub 2/-UO/sub 2/) is described, and results of nondestructive examinations and destructive examinations of selected rods after operation at 9 to 17 kw/ft to peak depletions of 9 x 10/sup 20/ fissions/cm/sup 3/ (38,000 Mwd/Tonne U + Th) are presented. It is concluded that performance capability of the duplex pellets is excellent. Fuel pellet integrity was well maintained and dimensional changes, fission gas release, and fuel microstructural changes compare favorably with previous solid fuel pellet tests associated with the LWBR development programs. 78 figures, 19 tables.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA). Bettis Atomic Power Div.
• DOE Contract Number: AC11-76PN00014
• OSTI ID: 6887014
• Report Number(s): WAPD-TM-1460; ON: DE83001848
• Country of Publication: United States
• Language: English

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