PARTISN results for the OECD/NEA 3-D extension C5G7 MOX benchmark

MCNP-A General Monte Carlo N-Particle Transport Code

Judith F. Briesmeister · 1993 · 5.1K citations

Natural Sciences, Nuclear Engineering, Physics +13

Benchmark specification for Deterministic 2-D/3-D MOX fuel assembly transport calculations without spatial homogenisation (C5G7 MOX)

E.E. Lewis, M. A. Smith, Nicholas Tsoulfanidis et al. · 2001 · 110 citations

Engineering, Materials Science, Mechanical Engineering +8

ANGULAR QUADRATURES FOR IMPROVED TRANSPORT COMPUTATIONS

I.K. Abu-Shumays · Transport Theory and Statistical Physics · 2001 · 36 citations · Full text

Engineering, Materials Science, Computational Physics +11

Transport calculations for nuclear analyses: Theory and guidelines for effective use of transport codes

R.D. O'Dell, R.E. Alcouffe · 1987 · 27 citations

Engineering, Nuclear Engineering, Physics +16