All skills
MCNP
Monte Carlo N-ParticleNPCILBARCIGCARWestinghouseL&T
A general-purpose Monte Carlo code for neutron, photon, electron and coupled transport calculations used across shielding, criticality and dosimetry.
Difficulty
Advanced
Salary premium
+32%
Demand score
92
Learning roadmap
1
Nuclear physics fundamentals
2
Monte Carlo transport theory
3
Geometry and material card modelling
4
Shielding and criticality problems
5
Tallies and variance reduction
6
Radiation protection applications
Courses
- MCNP Shielding Design
- Monte Carlo Methods for Engineers
Books
- MCNP Manual and Primer
- Nuclear Reactions for Engineering
Recommended projects
- Design a shielding layout for an SMR containment
- Replicate a neutron fluence benchmark
- Compare MCNP vs OpenMC on a criticality problem