  Graphite is important reactor material used as a neutron moderator in various
reactor designs. It is not only structural material used in previous reactors
design but even material to which attention is focused due to the very
high-temperature reactor design, which uses graphite as moderator and
reflector. Due to the well-characterised cross-section of graphite, it is also
a good candidate for neutron shaping experiments. In this kind of experiment,
the neutron spectra are modified to the unconventional shape of neutron spectra
which can be used to validate cross-section. This paper deals with validation
of neutron field in graphite block surrounded by driver core arranged in large
special core in LR-0 reactor. The experimentally determined shape of neutron
spectra and spatial distribution of neutron flux is compared with the
calculation. It is worth noting that the agreement for flux distribution is
satisfactory in regions below the moderator level.
