Determination of the residual content of fissile materials in fuel from spent fuel assemblies with high initial enrichment by the active neutron method

A stand and procedure for measuring the residual content of fissile materials in spent fuel assemblies from research and propulsion reactors are described. The results of experiments performed with spent and fresh fuel assemblies from the IRT reactor at the Moscow Engineering Physics Institute [MIFI...

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Veröffentlicht in:	Atomic energy (New York, N.Y.) N.Y.), 2013-10, Vol.114 (6), p.428-432
Hauptverfasser:	Bushuev, A. V., Kozhin, A. F., Glagovsky, E. M., Zubarev, V. N., Aleeva, T. B., Petrova, E. V., Rudenko, V. S., Smirnov, V. E., Malakhov, M. I.
Format:	Artikel
Sprache:	eng
Schlagworte:	Efficiency Engineering Experiments Hadrons Heavy Ions Irradiation Measurement techniques Methods Neutrons Nuclear Chemistry Nuclear Energy Nuclear fission Nuclear fuels Nuclear Physics Physics Physics and Astronomy Plutonium Polyethylene Radiation Radioactive wastes Reactors Spent reactor fuels Studies Uranium
Online-Zugang:	Volltext
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