Accuracy assessment of a new Monte Carlo based burnup computer code

详细信息	查看全文 | 推荐本文 |

• 作者：B. El Bakkari^a ; ^b ; ^{bakkari@cnesten.org.ma} ; T. ElBardouni^b ; B. Nacir^a ; C. ElYounoussi^a ; ^b ; Y. Boulaich^a ; ^b ; O. Meroun^b ; M. Zoubair^b ; E. Chakir^c
• 关键词：Burnup ; BUCAL1 ; VVER-1000 LEU ; MCNP ; NJOY99
• 刊名：Annals of Nuclear Energy
• 出版年：2012
• 期刊代码：1_03064549
• 类别：pw
• 出版时间：July, 2012
• 卷：45
• 期：Complete
• 页码：29-36
• 文件大小：2005 K

摘要

This study aims to test for the suitability and accuracy of a new home-made Monte Carlo burnup code, called BUCAL1, by investigating and predicting the neutronic behavior of a 鈥淰VER-1000 LEU Assembly Computational Benchmark鈥? at lattice level. BUCAL1 uses MCNP tally information directly in the computation; this approach allows performing straightforward and accurate calculation without having to use the calculated group fluxes to perform transmutation analysis in a separate code. ENDF/B-VII evaluated nuclear data library was used in these calculations. Processing of the data library is performed using recent updates of NJOY99 system. Code to code comparisons with the reported Nuclear OECD/NEA results are presented and analyzed.