Status and Scope of MONC Transport Code

TL;DR

MONC is a neutron transport code utilizing constructive solid geometry, advanced visualization, and benchmarking against experimental data, showing promising accuracy for reactor and shielding simulations.

Contribution

The paper introduces new geometric modeling features, a GUI, and benchmarking results for the MONC neutron transport code, enhancing its capabilities and validation.

Findings

Results of keff agree within ~3 mk with experiments

Code accurately simulates neutron flux and shielding

Benchmarking confirms reliability of the code

Abstract

$\underline{\textbf{MO}}$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.