Abstract
This paper presents the early development of a coupled
neutron / photon transport mode in the Serpent 2 Monte
Carlo code. The methodology covers the production of
prompt secondary gammas emitted in neutron interactions,
using the ENDF reaction sampling laws in ACE format cross
section libraries. The new transport mode is developed
mainly to account for the effect of gamma heating in
multi-physics simulations. Other potential applications
include radiation shielding and fusion neutronics. The
work is still under way, and at the time of this writing
the distributed version of Serpent 2 lacks the capability
to transport both neutrons and secondary photons
simultaneously. The methodology is instead tested and
demonstrated by dividing the simulation in two parts, and
the results are compared to reference MCNP calculations.
The test cases include a simple broomstick problem for
the comparison of photon emission spectra, and gamma flux
and heating calculations in an infinite BWR fuel lattice.
| Original language | English |
|---|---|
| Number of pages | 6 |
| Publication status | Published - 2017 |
| Event | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2017 - Jeju, Korea, Republic of Duration: 16 Apr 2017 → 20 Apr 2017 |
Conference
| Conference | International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2017 |
|---|---|
| Abbreviated title | M&C 2017 |
| Country/Territory | Korea, Republic of |
| City | Jeju |
| Period | 16/04/17 → 20/04/17 |