Behavior of (U,Pu)0/sub 2/ sphere-pac fuel, with plutonium in the large spheres only, in low burnup tests under pressurized water reactor conditions

Journal Article · Fri Oct 01 00:00:00 EDT 1982 · Nucl. Technol.; (United States)

OSTI ID:6101489

Der Linde, A V; Verheugen, J H.N.

Two irradiation tests were conducted in the pressurized water reactor loop of the High Flux Reactor at Petten to compare the low burnup (0.4% fima), high power (35 to 60 kW x m/sup -1/) performance of MO/sub 2/ sphere-pac fuel with the plutonium incorporated only in the large (1000-..mu..m) diameter spheres and that of homogeneously enriched UO/sub 2/ sphere-pac and pellet fuel. The fuel columns in the Zircaloy-4 clad pins were fabricated with a smear density of 87 to 88% of the theoretical UO/sub 2/ density. Postirradiation examinations showed that fission gas release, axial migration of cesium, and relocation of small (10- to 40-..mu..m) and medium (approx. =100-..mu..m) diameter spheres were considerably larger in the MO/sub 2/ sphere-pac pins than in the UO/sub 2/ sphere-pac pins Contrary to observations in the pellet pins, no hard mechanical fuel-cladding interaction has been observed in the sphere-pac pins. Although these tests showed the technical feasibility of the inhomogeneous MO/sub 2/ sphere-pac fuel pin, its further development seems appropriate only in connection with the use of recycle light water reactor fuel.

• Research Organization: Netherlands Energy Research Foundation, ECN, Materials Department, P.O. Box 1, 1755 ZG, Petten
• OSTI ID: 6101489
• Journal Information: Nucl. Technol.; (United States), Vol. 59:1
• Country of Publication: United States
• Language: English

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