Published October 2008 | Version v1
Journal article

Auto MOC-A 2D neutron transport code for arbitrary geometry based on the method of characteristics and customization of AutoCAD

  • 1. School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an Shaanxi 710049 (China)

Description

A new 2D neutron transport code AutoMOC for arbitrary geometry has been developed. This code is based on the method of characteristics (MOCs) and the customization of AutoCAD. The MOC solves the neutron transport equation along characteristic lines. It is independent of the geometric shape of boundaries and regions. So theoretically, this method can be used to solve the neutron transport equation in highly complex geometries. However, it is important to describe the geometry and calculate intersection points of each characteristic line with every boundary and region in advance. In complex geometries, due to the complications of treating the arbitrary domain, the selection of geometric shapes and efficiency of ray tracing are generally limited. The geometry treatment through the customization of AutoCAD, a widely used computer-aided design software package, is given in this paper. Thanks to the powerful capability of AutoCAD, the description of arbitrary geometry becomes quite convenient. Moreover, with the language Visual Basic for Applications (VBAs), AutoCAD can be customized to carry out the ray tracing procedure with a high flexibility in geometry. The numerical results show that AutoMOC can solve 2D neutron transport problems in a complex geometry accurately and effectively

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2008.04.014

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2008.04.014;
PII
S0029-5493(08)00272-0;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
238
Journal Issue
10
Journal Page Range
p. 2828-2833
ISSN
0029-5493
CODEN
NEDEAU

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
40005517
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
A CODES; COMPUTER-AIDED DESIGN; EFFICIENCY; GEOMETRY; NEUTRON TRANSPORT; NEUTRON TRANSPORT THEORY; SHAPE
Descriptors DEC
COMPUTER CODES; DESIGN; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; TRANSPORT THEORY

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.