Monte Carlo code for neutron and photon

B riesmeister, J. F. 1990. MCNP-A general Monte Carlo code for neutron and photon transport. Version 4.2. Technical Report LA-7396-M, Los Alamos National Laboratory. [Pg.440]

LASL Group TD-6, MCNP-A General Monte Carlo Code for Neutron and Photon Transport, LA-7396-M, Los Alamos Scientific Lab. (July 1978). [Pg.663]

Reactor physical characteristics have also drawn much attention. The control rod worth, including the differential worth and integral worth, were calculated by the Monte Carlo code for neutron and photon transport (MCNP) for the 2 MW TMSR-SE (Zhou and Liu, 2013). The measurement of the neutron energy spectrum was also theoretically and experimentally studied (Zhou, 2013). Parametric study of the thorium-uranium conversion rate was conducted to optimize the core structure for the improvement of the economics of the TMSR using the standardized computer analyses for licensing evaluation (SCALE) code (Wang and Cai, 2013). [Pg.399]

MCNP Monte Carlo code for neutron and photon transport... [Pg.406]

Big Chemical Encyclopedia