Sensitivity and Uncertainty Analyses of Lead Sample Reactivity Experiments at Kyoto University Critical Assembly

被引:12
作者
Pyeon, Cheol Ho [1 ]
Fujimoto, Atsushi [2 ]
Sugawara, Takanori [3 ]
Iwamoto, Hiroki [3 ]
Nishihara, Kenji [3 ]
Takahashi, Yoshiyuki [1 ]
Nakajima, Ken [1 ]
Tsujimoto, Kazufumi [3 ]
机构
[1] Kyoto Univ, Inst Res Reactor, Nucl Engn Sci Div, Kumatori, Osaka 5900494, Japan
[2] Kyoto Univ, Grad Sch Energy Sci, Dept Fundamental Energy Sci, Sakyo Ku, Kyoto 6068501, Japan
[3] Japan Atom Energy Agcy, Nucl Sci & Engn Ctr, Tokai, Ibaraki 3191194, Japan
关键词
Lead; covariance data; Kyoto University Critical Assembly; ACCELERATOR-DRIVEN SYSTEM; NUCLEAR-DATA LIBRARY; CROSS-SECTIONS; PROTONS; TRANSMUTATION; JENDL-4.0; SCIENCE; BISMUTH; IMPACT;
D O I
10.1080/00295639.2016.1272976
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
Sensitivity and uncertainty analyses of lead (Pb) isotope cross sections are conducted with the use of sample reactivity experiments at the Kyoto University Critical Assembly (KUCA). With the combined use of the SRAC2006 and MARBLE code systems, attempts are made to precisely examine the contributions of the reactions and energy regions of Pb isotope cross sections to reactivity based on the covariance data of JENDL-4.0. Moreover, the effect of decreasing uncertainty is discussed in terms of the accuracy of sample reactivity by applying the cross-section adjustment method to the uncertainty analyses. From the results of the sensitivity and uncertainty analyses, the reliability of Pb isotope cross sections, such as the Pb isotope covariance data of JENDL-4.0, is compared with the JENDL-3.3, ENDF/B-VII.0, and JEFF-3.1 libraries. Additionally, the numerical results reveal the applicability of the sensitivity and uncertainty analyses to the thermal neutron spectrum cores, such as the KUCA core, and demonstrate the improvement in the calculation results generated by the cross-section adjustment.
引用
收藏
页码:460 / 472
页数:13
相关论文
共 39 条
[1]   MYRRHA: A European experimental ADS for R&D applications - Status at mid-2005 and prospective towards implementation [J].
Abderrahim, Hamid Ait ;
D'Hondt, Pierre .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2007, 44 (03) :491-498
[2]   Nuclear data sensitivity, uncertainty and target accuracy assessment for future nuclear systems [J].
Aliberti, G. ;
Palmiotti, G. ;
Salvatores, M. ;
Kim, T. K. ;
Taiwo, T. A. ;
Anitescu, M. ;
Kodeli, I. ;
Sartori, E. ;
Bosq, J. C. ;
Tommasi, J. .
ANNALS OF NUCLEAR ENERGY, 2006, 33 (08) :700-733
[3]   Impact of nuclear data uncertainties on transmutation of actinicles in accelerator-driven assemblies [J].
Aliberti, G ;
Palmiotti, G ;
Salvatores, M ;
Stenberg, CG .
NUCLEAR SCIENCE AND ENGINEERING, 2004, 146 (01) :13-50
[4]   Sensitivity- and uncertainty-based criticality safety validation techniques [J].
Broadhead, BL ;
Rearden, BT ;
Hopper, CM .
NUCLEAR SCIENCE AND ENGINEERING, 2004, 146 (03) :340-366
[5]  
Cacuci D., 2005, Sensitivity and uncertainty analysis, Volume II: applications to large-scale systems
[6]  
Cacuci D, 2003, Sensitivity and Uncertainty Analysis: Theory, VI
[7]   Best-Estimate Model Calibration and Prediction Through Experimental Data Assimilation I: Mathematical Framework [J].
Cacuci, Dan G. ;
Ionescu-Bujor, Mihaela .
NUCLEAR SCIENCE AND ENGINEERING, 2010, 165 (01) :18-44
[8]   SENSITIVITY THEORY FOR GENERAL SYSTEMS OF NON-LINEAR EQUATIONS [J].
CACUCI, DG ;
WEBER, CF ;
OBLOW, EM ;
MARABLE, JH .
NUCLEAR SCIENCE AND ENGINEERING, 1980, 75 (01) :88-110
[9]   On the neutron kinetics and control of accelerator-driven systems [J].
Cacuci, DG .
NUCLEAR SCIENCE AND ENGINEERING, 2004, 148 (01) :55-66
[10]   ADVANCES IN GENERALIZED PERTURBATION THEORY [J].
CECCHINI, GP ;
SALVATORES, M .
NUCLEAR SCIENCE AND ENGINEERING, 1971, 46 (02) :304-+