Nuclear data uncertainty and sensitivity analysis of the VHTRC benchmark using SCALE

被引:18
作者
Bostelmann, Friederike [1 ]
Strydom, Gerhard [2 ]
机构
[1] Gesell Anlagen & Reaktorsicherheit GRS gGmbH, D-85748 Garching, Germany
[2] INL, Nucl Sci & Engn Div, Idaho Falls, ID 83401 USA
关键词
HTGR; VHTRC; SCALE; Uncertainty analysis; Sensitivity analysis; CRITICALITY CALCULATIONS; CROSS-SECTION;
D O I
10.1016/j.anucene.2017.06.052
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 Very High Temperature Critical Assembly (VHTRC) experiment represents one of the few data sets available for the validation of HTGR lattice physics. Within the framework of the IAEA Coordinated Research Project on HTGR Uncertainty Analysis in Modeling, uncertainty and sensitivity analyses of this graphite-moderated facility are performed as the validation reference to the prismatic MHTGR-350 fuel block calculations. Nominal multi-group and continuous-energy criticality calculations with the KENO-VI Monte Carlo code of the SCALE code package are compared with the continuous-energy Monte Carlo Code Serpent. Good agreement with a maximum difference of 250 pcm is obtained. The experimental data set, however, differs by several hundred pcm with the results of both codes when using the ENDF-VII.0 library. When using ENDF/B-VII.1 data, this difference is reduced to a few hundred pcm and the calculations lie within the experimental error bars. Uncertainties of the VHTRC multiplication factors due to uncertainties in nuclear data are determined with SAMPLER/KENO-VI of SCALE 6.2 and with continuous-energy TSUNAMI of SCALE 6.2. For all experimental configurations, the obtained uncertainty is found to be 0.58% when using ENDF/B-VII.0 data. The top contributor to this uncertainty is the average number of neutrons per fission event of U-235. With ENDF/B-VII.1 data, uncertainties of about 0.66% are obtained in particular due to an increased uncertainty of U-235 nu-bar in the latest ENDF release. When considering these nuclear data uncertainties, the obtained l sigma uncertainty intervals are overlapping with the experimental error bars. (C) 2017 Elsevier Ltd. All rights reserved.
引用
收藏
页码:317 / 329
页数:13
相关论文
共 15 条
[1]   A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT [J].
Aufiero, Manuele ;
Bidaud, Adrien ;
Hursin, Mathieu ;
Leppanen, Jaakko ;
Palmiotti, Giuseppe ;
Pelloni, Sandro ;
Rubiolo, Pablo .
ANNALS OF NUCLEAR ENERGY, 2015, 85 :245-258
[2]  
Bostelmann F., 2015, P ANS MC2015 NASHV T
[3]   Criticality calculations of the Very High Temperature Reactor Critical Assembly benchmark with Serpent and SCALE/KENO-VI [J].
Bostelmann, Friederike ;
Hammer, Hans R. ;
Ortensi, Javier ;
Strydom, Gerhard ;
Velkov, Kiril ;
Zwermann, Winfried .
ANNALS OF NUCLEAR ENERGY, 2016, 90 :343-352
[4]   Review of the natC(n,γ) cross section and criticality calculations of the graphite moderated reactor BR1 [J].
Diez, C. J. ;
Stankovskiy, A. ;
Malambu, E. ;
Zerovnik, G. ;
Schillebeeckx, P. ;
Van den Eynde, G. ;
Heyse, J. ;
Cabellos, O. .
ANNALS OF NUCLEAR ENERGY, 2013, 60 :210-217
[5]   Impact of Revised Thermal Neutron Capture Cross Section of Carbon Stored in JENDL-4.0 on HTTR Criticality Calculation [J].
Goto, Minoru ;
Shimakawa, Satoshi ;
Nakao, Yasuyuki .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2011, 48 (07) :965-969
[6]  
Ivanov K., 2013, SPECIFICATION SUPPOR, VI
[7]  
Leppanen J., 2007, THESIS
[8]   The Serpent Monte Carlo code: Status, development and applications in 2013 [J].
Leppanen, Jaakko ;
Pusa, Maria ;
Viitanen, Tuomas ;
Valtavirta, Ville ;
Kaltiaisenaho, Toni .
ANNALS OF NUCLEAR ENERGY, 2015, 82 :142-150
[9]  
NEA, 2013, INT HDB EV REACT PHY
[10]  
Ortensi J., 2013, PRISMATIC COUPLED NE