Status and Scope of MONC Transport Code.
$\underline{\textbf{MO}}$nte-carlo $\underline{\textbf{N}}$ucleon transport $\underline{\textbf{C}}$ode (MONC) for nucleon transport is being developed for several years. Constructive Solid Geometry concept is applied with the help of solid bodies. Union, subtraction and intersection Boolean operations are used to construct heterogeneous zones. Scaling, rotation, and translation operation of the basic bodies are allowed to construct more complex zones. Module of repetitive structure for lattice, core calculations in reactor and detector simulation is developed. Graphical User Interface along with visualization tools is developed to make input, construction and display of geometry, and analysis of output data. Low energy neutron transport module is developed using continuous linearly interpolable point neutron cross section data below 20MeV neutron energy. The code is benchmarked for simulation of accelerator driven sub-critical system, neutron shielding, heat and neutron flux distribution and keff of the critical assemblies. It is observed that results of keff are in agreement within $\sim$ 3mk with experimental results of critical assemblies as well as the values obtained from MCNP.