Cover of the work “Determination of the content of 235U, 236U, 237Np, 238U in spent IRT fuel assemblies by the method of re-irradiation in the reactor and subsequent gamma-spectrometric measurements”. Author: Li Rundong. Degree: Candidate of Sciences. Year: 2004

Determination of the content of 235U, 236U, 237Np, 238U in spent IRT fuel assemblies by the method of re-irradiation in the reactor and subsequent gamma-spectrometric measurements

Moscow

128 pp.

Determination of the content of 235U, 236U, 237Np, 238U in spent IRT fuel assemblies by the method of re-irradiation in the reactor and subsequent gamma-spectrometric measurements — Li Rundong — 2004 — Russian Dissertation Library