A New Coupling CFD/Monte-Carlo Neutron Transport Scheme, Application to a Single Fuel Rod Problem

被引：0

作者：

Henry, Romain ^{[1
]}

Tiselj, Iztok ^{[1
]}

机构：

[1] Jozef Stefan Inst, Jamova 39, SI-1000 Ljubljana, Slovenia

来源：

23RD INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2014) | 2014年

关键词：

D O I：

暂无

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The work presented here, focuses on the presentation of the coupling scheme developed between the Computational Fluid Dynamic (CFD) code ANSYS CFX and the Monte Carlo neutron transport code TRIPOLI. The scheme is tested on a single fuel rod problem derived from the OECD/NEA and US NRC PWRMOX/UO2 core transient Benchmark. Prediction capabilities of our Coupled system are compared with results available in the literature.

引用

页数：8

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