Application of Monte Carlo Method for Burnup Dependent Full Core Neutronic Analysis of PBMR

被引：0
|
作者：
Tombakoglu, Mehmet [1 ]
Celik, Cihangir [1 ,2 ]
机构：
[1] Hacettepe Univ, Dept Nucl Engn, TR-06800 Ankara, Turkey
[2] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
来源：
24TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2015) | 2015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：
In this study, computational results of burnup dependent full core neutronic analysis of Pebble Bed Modular Reactor (PBMR) are presented. The calculations were performed by the MCNP-4b and BURN-HUNEM codes. BURN-HUNEM code was developed and utilized to perform depletion calculations using the cross section data generated by MCNP-4b to include double heterogeneity effect on neutronic parameters. The results for equilibrium cycle core composition and burnup were presented for once-through-then-out (OTTO) and Mehrfach-DUrchLauf (MEDUL) i.e., multi-pass, fuel cycle strategies.
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页数：6
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