Concepedia
Journal of Nuclear Materials · 2004 · 24 citations · 9 references
EngineeringNuclear EngineeringNuclear Fuel CycleBattery SystemsBattery Technology
9
MCNP-A General Monte Carlo N-Particle Transport Code
Judith F. Briesmeister · 1993 · 5.1K citations
Natural Sciences, Nuclear Engineering, Physics +13
Cross-Section Evaluations to 150 MeV for Accelerator-Driven Systems and Implementation in MCNPX
M. B. Chadwick, P.G. Young, Satoshi Chiba et al. · Nuclear Science and Engineering · 1999 · 346 citations
Engineering, Nuclear Engineering, Physics +17
Advanced Monte Carlo procedure for the IFMIF d-Li neutron source term based on evaluated cross section data
S.P. Simakov, U. Fischer, Ulrich von Möllendorff et al. · Journal of Nuclear Materials · 2002 · 71 citations
Engineering, Nuclear Engineering, Physics +14
Development of Methods for Calculation of Deuteron-Lithium and Neutron-Lithium Cross Sections for Energies up to 50 MeV
A.Yu. Konobeyev, Yu.A. Korovin, P. Pereslavtsev et al. · Nuclear Science and Engineering · 2001 · 56 citations
Natural Sciences, Physics, Nuclear Physics +16
Evaluated nuclear data files for accelerator driven systems and other intermediate and high-energy applications
Yu.A. Korovin, A.Yu. Konobeyev, P. Pereslavtsev et al. · Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment · 2001 · 45 citations
Natural Sciences, Nuclear Engineering, Physics +14