New developments of the MCNP/CTF/NEM/NJOY code system – Monte Carlo based coupled code for high accuracy modeling

MCNP-A General Monte Carlo N-Particle Transport Code

Judith F. Briesmeister · 1993 · 5.1K citations

Natural Sciences, Nuclear Engineering, Physics +13

Thermal Neutron Scattering Data for the Moderator Materials H2O, D2O and ZrHx in ENDF-6 Format and as ACE Library for MCNP(X) Codes

M. Mattes, J. Keinert · 2005 · 59 citations · Full text

Natural Sciences, Materials Science, Physics +17

Application of continuous-energy Monte Carlo code as a cross-section generator of BWR core calculations

Masayuki Tohjoh, M. Watanabe, Akio Yamamoto · Annals of Nuclear Energy · 2005 · 28 citations

Engineering, Nuclear Engineering, Physics +14

Nodal kinetics model upgrade in the Penn State coupled TRAC/NEM codes

Tara M. Beam, Kostadin Ivanov, A.J. Baratta et al. · Annals of Nuclear Energy · 1999 · 21 citations

Natural Sciences, Nuclear Engineering, Physics +8

Improvements and applications of COBRA-TF for stand-alone and coupled LWR safety analyses

Maria Avramova, D. Cuervo, Kostadin Ivanov · 2006 · 14 citations

Engineering, Aerospace Engineering, Nuclear Engineering +17