Concepedia

Development of the MCNPX depletion capability: A Monte Carlo linked depletion method that automates the coupling between MCNPX and CINDER90 for high fidelity burnup calculations

Michael L Fensin

2008 · 19 citations · 26 references

Concepts

References

26

MCNP-A General Monte Carlo N-Particle Transport Code

Judith F. Briesmeister · 1993 · 5.1K citations

, , +15

Probability and Statistics for Engineers and Scientists.

Richard J. Beckman, Ronald E. Walpole, Raymond H. Meyers · Journal of the American Statistical Association · 1973 · 2.9K citations

, , +12

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

M. B. Chadwick, P. Obložinský, M. Herman et al. · Nuclear Data Sheets · 2006 · 2.2K citations · Full text

, , +7

<i>Introduction to Nuclear Engineering</i>

John R. Lamarsh, E. Melkonian · Physics Today · 1977 · 602 citations

, , +21

ORIGEN2: A Versatile Computer Code for Calculating the Nuclide Compositions and Characteristics of Nuclear Materials

A.G. Croff · Nuclear Technology · 1983 · 510 citations

, , +19