Description
Table of contents:
Contents .......................................................................................................................................... 4
Introduction ..................................................................................................................................... 8
Section 1: Basic Concepts ............................................................................................................... 81.1 Geometry ............................................................................................................................... 8
1.1.1 Simplest possible input file............................................................................................. 8
1.1.2 Running MCNP - Simplest Case ................................................................................... 91.1.3 Simple Input File .......................................................................................................... 12
1.1.4 Running and plotting MCNP geometries ..................................................................... 14
1.1.5 Surfaces and Complicated Cells: Intersections and Unions ......................................... 17
1.1.6 Duplicate Cells, Compliments and Translations: LIKE BUT and TRCL .................... 22
1.1.7 Filled Cells: Universes.................................................................................................. 26
1.1.8 Lattice Geometries ........................................................................................................ 32
1.1.9 Fully Specified Lattice Geometries .............................................................................. 40
1.2 Materials and Cross Sections .............................................................................................. 45
1.2.1 Specifying Materials ..................................................................................................... 45
1.2.2 Neutron cross sections .................................................................................................. 46
1.2.3 Low-energy neutron problems - thermal free gas treatment ........................................ 49
1.2.4 Low-energy neutron problem data - S(α,β) thermal treatment .................................... 50
1.2.5 Photon cross sections .................................................................................................... 53
1.2.6 Electron stopping powers for coupled photon and electron problems ......................... 57
1.2.7 Data and models for Ions and Charged Particles .......................................................... 61
1.2.8 Additional data diagnostics and recommendations ...................................................... 62
1.3 Sources ................................................................................................................................ 63
1.3.1 SDEF Fixed Sources ..................................................................................................... 63
1.3.2 SDEF Source Distributions .......................................................................................... 66
1.3.3 SDEF Dependent Distributions: DS ............................................................................. 69
1.3.4 Criticality Sources ........................................................................................................ 71
1.3.5 Surface Source Read and Write (SSR, SSW) ......................................................... 77
1.3.6 Checking sources .................................................................................................... 87
1.4 Output and Tallies ................................................
Author: John S. Hendricks, Martyn T. Swinhoe, Andrea Favalli
Publisher: Springer
Published: 09/28/2022
Pages: 307
Binding Type: Hardcover
Weight: 1.39lbs
Size: 9.21h x 6.14w x 0.75d
ISBN13: 9783031041280
ISBN10: 3031041283
BISAC Categories:
- Science | Physics | Nuclear
- Technology & Engineering | Power Resources | Nuclear
- Technology & Engineering | Engineering (General)
About the Author
Dr. John S. Hendricks has been one of the principal developers/leader of MCNP(R) software for more than 30 years. In addition, he has taught more than 100 MCNP classes and consulted internationally on the effective use of MCNP software. In 2007, he was elected fellow to the American Nuclear Society for his contributions to Monte Carlo development.
Dr. Martyn T. Swinhoe was awarded the Vincent J. DeVito Distinguished Service Award in 2017 from the Institute for Nuclear Materials Management for--among many other achievements--pioneering the use of MCNP software for instrument design and enhancing the analysis of existing data sets to draw additional conclusions for nuclear materials management.
Dr. Andrea Favalli was elected fellow to the American Physical Society in 2020 for his outstanding application of the methods and underlying science of nuclear physics to the crucial issues of nuclear safeguards and security. His work has focused on nondestructive assay of nuclear materials, ranging from new analytical approaches to experimental measurements.