Fission source spatial distribution for the center horizontal slice.

.. _fig4a4:

.. figure:: figs/fig4a4.png

:align: center

:width: 60 %

Fission source energy distribution for the center voxel.

MAVRIC transport calculations

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

Two MAVRIC calculations will be done—one that calculates the doses seen

at the detector and one that computes mesh tallies of doses over the

entire building. They will share the same materials, geometry, and

source but will have different tally and variance reduction options.

The two-room building will be a simple model using concrete-block walls,

a concrete floor, and a steel roof, with dimensions shown in

:numref:`fig4a5`. The building exterior dimensions are 1200 cm long,

600 cm wide, and 300 cm high above the ground. The exterior and interior

walls are all made of a double layer of typical concrete blocks (total

of 40 cm thick.) Concrete blocks are typically 39×19×19 cm and weigh

~13.5 kg, since they have a volume fraction of 33.2%. The floor is made

of poured concrete, extending 60 cm into the ground. The roof and the

exterior door (120 cm wide and 210 cm tall) are made of 1/8 in. (0.3175

cm) thick steel. The experiment room on the left connects to the control

room on the right through a maze that prevents radiation streaming.

Assume that the critical experiment was in the center of the experiment

room, 100 cm above the floor. Assume the detector in the control room is

a 30 cm diameter sphere located at position (1145, 55, 285).

.. _fig4a5:

.. figure:: figs/fig4a5.png

:align: center

Coordinates of the floor, walls, ceiling, and door of the simple block building model (in cm).

If the MAVRIC transport calculation is not in the same file as the CSAS6 calculation, the MAVRIC input would start by moving the KENO-VI results into the SCALE temporary area: