Quantifying fissile content in spent nuclear fuel using 252Cf interrogation witih prompt neutron detection [electronic resource].
Published
Washington, D.C. : United States. Dept. of Energy, 2011. Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Published through SciTech Connect. 10/04/2011. "la-ur-11-05673" " la-ur-11-5673" Global 2011 ; December 11, 2011 ; Makuhari Messe, Chiba, Japan. Tobin, Stephen J; Menlove, Howard O; Hu, Jianwei.