The MCNP Monte Carlo Program
(2012) p.153-172- Abstract
Monte Carlo N-Particle (MCNP) is a Monte Carlo code package allowing coupled neutron, photon, and electron transport calculations. Also, the possibility of performing heavy charged particle transport calculations was recently introduced with the twin MCNPX code package. An arbitrary three-dimensional problem can be formulated through the use of surfaces defining building blocks (“cells” that are assigned density, material, and relevant cross-section tables. The source can be specified as point, surface, or volumes using generic or as a phase/space file.
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https://lup.lub.lu.se/record/575407cf-aa98-41a7-8d68-85f6fee37589
- author
- af Rosenschöld, Per Munck LU and Larsson, Erik LU
- organization
- publishing date
- 2012-01-01
- type
- Chapter in Book/Report/Conference proceeding
- publication status
- published
- subject
- host publication
- Monte Carlo Calculations in Nuclear Medicine : Applications in Diagnostic Imaging - Applications in Diagnostic Imaging
- editor
- Ljungberg, Michael ; Strand, Sven-Erik and King, Michael A
- edition
- 2nd
- pages
- 153 - 172
- publisher
- CRC Press/Balkema
- external identifiers
-
- scopus:85135640995
- ISBN
- 9781439841105
- 9781439841099
- DOI
- 10.1201/b13073-14
- language
- English
- LU publication?
- yes
- additional info
- Publisher Copyright: © 2013 by Taylor and Francis Group, LLC.
- id
- 575407cf-aa98-41a7-8d68-85f6fee37589
- date added to LUP
- 2023-07-19 17:12:36
- date last changed
- 2024-01-05 03:34:13
@inbook{575407cf-aa98-41a7-8d68-85f6fee37589, abstract = {{<p>Monte Carlo N-Particle (MCNP) is a Monte Carlo code package allowing coupled neutron, photon, and electron transport calculations. Also, the possibility of performing heavy charged particle transport calculations was recently introduced with the twin MCNPX code package. An arbitrary three-dimensional problem can be formulated through the use of surfaces defining building blocks (“cells” that are assigned density, material, and relevant cross-section tables. The source can be specified as point, surface, or volumes using generic or as a phase/space file.</p>}}, author = {{af Rosenschöld, Per Munck and Larsson, Erik}}, booktitle = {{Monte Carlo Calculations in Nuclear Medicine : Applications in Diagnostic Imaging}}, editor = {{Ljungberg, Michael and Strand, Sven-Erik and King, Michael A}}, isbn = {{9781439841105}}, language = {{eng}}, month = {{01}}, pages = {{153--172}}, publisher = {{CRC Press/Balkema}}, title = {{The MCNP Monte Carlo Program}}, url = {{http://dx.doi.org/10.1201/b13073-14}}, doi = {{10.1201/b13073-14}}, year = {{2012}}, }