Monte Carlo Modelling of Increasing Void Fraction in 100% MOX ABWR: Lessons Drawn from the FUBILA Program

被引:8
作者
Blaise, Patrick [1 ]
Thiollay, Nicolas [2 ]
Fougeras, Philippe [1 ]
机构
[1] French Atom Energy Commiss Nucl Energy Directorat, DEN DER SPRC Reactor Phys & Cycle Serv, F-13108 St Paul Les Durance, France
[2] French Atom Energy Commiss Nucl Energy Directorat, DEN DER SPEX Expt Phys Serv, F-13108 St Paul Les Durance, France
关键词
100% MOX; ABWR; FUBILA; JEFF3.1.1; TRIPOLI4; Monte Carlo; EOLE;
D O I
10.3327/jnst.47.558
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 French Atomic Energy Commission CEA and the Japanese Incorporated Administrative Agency JNES (Japan Nuclear Energy Safety Organisation) have undertaken first-of-a-kind full MOX core physics experiments, FUBILA, in the EOLE critical facility of the CEA Cadarache Centre. The experiments have been designed to obtain core physics data under high-burn-up 9 x 9 and 10 x 10 BWR MOX assemblies operating conditions. The experimental program, consisting of eight different core configurations, started in January 2005 and ended on September 1, 2006. The analysis of the void increase part of the experimental data between 0 and 70% void has been carried out using the French TRIPOLI-4.5 continuous-energy Monte Carlo calculation code with the newly released JEFF3.1.1 nuclear data library. The average C/E discrepancies obtained on critical masses, reactivity worth, and pin-by-pin power distributions enable us to estimate all the integral and local parameters with uncertainties largely within the target uncertainties, demonstrating the capability of the code to treat complex geometries with a high degree of accuracy. Additional k(eff) calculations performed with the latest ENDF/B-VII evaluation exhibit a clear tendency to overestimate the k(eff) by about 500 to 650 pcm and the void worth by more than 4%, showing that the JEFF3.1.1 library is more precise for MOX lattices.
引用
收藏
页码:558 / 569
页数:12
相关论文
共 19 条
[1]  
BERNARD D, 2007, JEFDOC1226
[2]  
BERNARD D, 2007, P INT C NUCL DAT ND
[3]  
BLAISE P, 2004, P ICONE12 INT C NUCL
[4]  
BLAISE P, 2009, P INT C ADV NUCL INS
[5]  
BLAISE P, 2009, P INT C ADV NUCL POW
[6]  
Both J.P., 1994, Proceedings of the 8th International Conference on Radiation Shielding, P373
[7]  
CATHALAU S, 2002, P INT C NEW FRONT NU
[8]  
CATHALAU S, 2004, P INT C ADV REACT PH
[9]   The reactivity temperature coefficient analysis in light water moderated UO2 and UO2-PUO2 lattices [J].
Erradi, L ;
Santamarina, A ;
Litaize, O .
NUCLEAR SCIENCE AND ENGINEERING, 2003, 144 (01) :47-73
[10]  
FOUGERAS P, 2005, P INT C ICONE13 BEIJ