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contributor authorZhou, Xinyu
contributor authorLiu, Zhouyu
contributor authorCao, Lu
contributor authorCao, Liangzhi
contributor authorWu, Hongchun
contributor authorHan, Yu
contributor authorTang, Chuntao
date accessioned2022-02-04T14:27:58Z
date available2022-02-04T14:27:58Z
date copyright2020/02/24/
date issued2020
identifier issn2332-8983
identifier otherners_006_02_021901.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4273709
description abstractThe constructive solid geometry (CSG) method is widely used in the Monte Carlo community because of its geometry flexibility. As the requirements of designing new reactors and development of deterministic methods, the CSG method is adopted for the geometry modeling in the deterministic numerical nuclear reactor physics codes to construct complex geometries in recent years. In the new developed numerical nuclear reactor physics code NECP-X, the CSG method is also implemented to expand its geometric modeling capability, but it is difficult to efficiently calculate the volume of complex geometries. This work develops a new efficient method for calculating volume of arbitrarily complex geometries for NECP-X. Rather than implementing the sampling method, the new developed method is based on the characteristic ray information, which is used for the method of characteristics (MOC) sweeping in NECP-X. The implementation shows that this method is very convenient to be applied to the MOC codes. A set of cases such as pin-cell and hexagonal rod-bundle assembly problems are tested to show the accuracy and performance.
publisherThe American Society of Mechanical Engineers (ASME)
titleMethod Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X
typeJournal Paper
journal volume6
journal issue2
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4045035
page21901
treeJournal of Nuclear Engineering and Radiation Science:;2020:;volume( 006 ):;issue: 002
contenttypeFulltext


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