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, Candidate of Sciences dissertation
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