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Springer Publishing Company

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Recommended values of the delayed neutron yield for: U-235; U-238 and Pu-239

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Energy dependence of relative abundances and periods of delayed neutrons from neutron-induced fission of 235 U, 238 U, 239 Pu in 6- and 8-group model representation

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Mass spectrometric studies on irradiated (U, Pu) mixed carbide fuel of FBTR

By Balasubramanian R.   Raj D. Darwin Albert   Nalini S.   Baba M. Sai  

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Comprehensive evaluation of the state of spent VVR fuel assemblies from first-generation nuclear submarines

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