Out-of-pile chemical compatibility of hyperstoichiometric (Pu0.7U0.3)C with stainless steel cladding and sodium coolant

Ganguly, C. ; Sengupta, A. K. (1988) Out-of-pile chemical compatibility of hyperstoichiometric (Pu0.7U0.3)C with stainless steel cladding and sodium coolant Journal of Nuclear Materials, 158 . pp. 159-165. ISSN 0022-3115

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Official URL: http://linkinghub.elsevier.com/retrieve/pii/002231...

Related URL: http://dx.doi.org/10.1016/0022-3115(88)90165-1

Abstract

Chemical compatibility experiments of the hitherto unknown fuel (Pu0.7U0.3)C1+x with sodium coolant and SS 316 (20% cold-worked) cladding were carried out at 973 K for 1000 h for its out-of-pile 'proof testing'. Any possible chemical interaction was assessed by metallographic examination and microhardness measurements of SS 316 cladding specimens. Hyperstoichiometric (Pu0.7U0.3)C containing upto 0.7% oxygen and 20% mixed sesquicarbide (M2C3) did not interact at all with sodium and caused insignificant carburization of the SS 316 cladding. Mixed carbide pellets containing high 'O' (~1%) and high M2C3(~60%) caused clad carburization to a depth of around 90 μm. These experiments generated valuable informations in support of choosing plutonium rich mixed carbide as the driver fuel for the fast breeder test reactor (FBTR).

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