SUMMARY OF UO$sub 2$-STAINLESS STEEL DISPERSION ELEMENT IRRADIATION EXPERIMENTS | Zendy

V.O. Haynes | Zendy; F.H. Neill | Zendy; L.D. Schaffer | Zendy

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SUMMARY OF UO$sub 2$-STAINLESS STEEL DISPERSION ELEMENT IRRADIATION EXPERIMENTS

Author(s) -

V.O. Haynes,

F.H. Neill,

L.D. Schaffer

Publication year - 1958

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/4134779

Subject(s) - swelling , irradiation , blisters , materials science , cracking , fission , dispersion (optics) , nuclear fission product , fission products , metallurgy , radiochemistry , forensic engineering , nuclear engineering , composite material , chemistry , nuclear physics , engineering , neutron , physics , optics

A search of the literature to obtain information concerning enriched UO/ sub 2/-- stainless-steel dispersion type fuel elements has disclosed five programs which have pertinent information. The primary aim of the search was to discover maximum burn-ups and temperatures for safe use of this type of element. Tests were labeled a failure if swelling, cracking or fission-product release resulted from the irradiation. Moderate swelling or blisters without the other indications was called a slight failure since funther irradiation or higher temperature would undoubtedly cause complete failure. (auth

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