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Title: The MCNP6 Book On Unstructured Mesh Geometry: User's Guide for MCNP 6.2.1

Abstract

Los Alamos National Laboratory’s (LANL) Monte Carlo N-Particle R (MCNP R ) transport code has a more general geometry capability than has been available in most combinatorial geometry codes [1]. In addition to the capability of combining several predefined geometric bodies, as in a combinatorial scheme, MCNP6 [2] gives the user the added flexibility of defining geometric regions from all the first and second degree surfaces of analytical geometry and elliptical tori and then combining them with Boolean operators. This decades-old constructive solid geometry (CSG) capability has been well-tested and verified. However, it has long been recognized that as the model complexity increases, this process of describing the geometry is difficult, tedious, time-consuming, and error prone[3, 4, 5]. Consequently, innovators have taken on the task of developing a better way to construct geometries, not only in MCNP6, but other particle transport codes as well

Authors:
 [1]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1467189
Report Number(s):
LA-UR-18-27630
DOE Contract Number:  
AC52-06NA25396
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
97 MATHEMATICS AND COMPUTING

Citation Formats

Martz, Roger Lee. The MCNP6 Book On Unstructured Mesh Geometry: User's Guide for MCNP 6.2.1. United States: N. p., 2018. Web. doi:10.2172/1467189.
Martz, Roger Lee. The MCNP6 Book On Unstructured Mesh Geometry: User's Guide for MCNP 6.2.1. United States. doi:10.2172/1467189.
Martz, Roger Lee. Thu . "The MCNP6 Book On Unstructured Mesh Geometry: User's Guide for MCNP 6.2.1". United States. doi:10.2172/1467189. https://www.osti.gov/servlets/purl/1467189.
@article{osti_1467189,
title = {The MCNP6 Book On Unstructured Mesh Geometry: User's Guide for MCNP 6.2.1},
author = {Martz, Roger Lee},
abstractNote = {Los Alamos National Laboratory’s (LANL) Monte Carlo N-Particle R (MCNP R ) transport code has a more general geometry capability than has been available in most combinatorial geometry codes [1]. In addition to the capability of combining several predefined geometric bodies, as in a combinatorial scheme, MCNP6 [2] gives the user the added flexibility of defining geometric regions from all the first and second degree surfaces of analytical geometry and elliptical tori and then combining them with Boolean operators. This decades-old constructive solid geometry (CSG) capability has been well-tested and verified. However, it has long been recognized that as the model complexity increases, this process of describing the geometry is difficult, tedious, time-consuming, and error prone[3, 4, 5]. Consequently, innovators have taken on the task of developing a better way to construct geometries, not only in MCNP6, but other particle transport codes as well},
doi = {10.2172/1467189},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2018},
month = {8}
}

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