1. Case Monte Carlo Simulations 4/17/2008

2. Toolbox MCNP5 – the grunt work Polimi – low energy stuff Matlab – post processing

3. MCNP/Polimi Procedure Create an input file for MCNP with geometry, filling material, etc each stored in a card – Polimi has set sources so you can call a Cf-252 source whereas in MCNP you define a Watt fission spectrum for your source Run through Polimi and get out a data file with position, timing and particle information

4. Polimi Output

5. 133312410 1xx2 2xxx3 30 4xxx3 5xx2 6xx2 7xx2 8x1 9xxx3 100ns bins Event History Events that meet the 2MeV cut Time Projection Event Projection Processing

6. Reproduce UCSB plots Two runs (a) with GdCL3 0.2% by mass and (b) just water 4000 total events (cuts down on iteration time) Same cylinder size and source placement

8. Timing distribution

9. Thrown Neutron Spectrum

10. Rate vs Multiplicity