algorithmcellmontecarlosurface

MCNP 6 - Doubts about cells


I'm trying to insert a cylinder in the MCNP 6 code. I believe I defined the surfaces and planes correctly. What could be wrong?

Surfaces:

520 cz  435  1

5020 px  435

6020 px  450

Cells:
81     5  -1.2250E-3       (-520 5020 -6020)
99    5  -1.2250E-3              -3552 1050 -110
                                 (110:-1050:-33:33:29:-35:36)                            
                                 (110:-1050:-30:34:-35:36)
                                 (110:-109:-29:30:-35:36)
                                 (109:-1050:-29:30:31:-35)
                                 (109:-1050:-29:30:-32:36)
                                 (110:-1050:-33:29:-35:36)
                                 (520:-5020:6020)

What could be wrong?


Solution

  • Generating MCNP decks can be very prone to mistakes for beginners. Using a Python library like CardSharp for generating MCNP input decks can be especially useful for MCNP beginners: https://github.com/pnnl/CardSharpForMCNP.

    It supports all geometry primitives and has a large materials library. Source and tally support is currently mainly geared towards detector models. Cards/features that are not yet supported can be easily inserted as raw strings. Comprehensive examples are provided.

    Full disclosure: I am the developer of the library.