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Author:

Wan, Chenghui (Wan, Chenghui.) | Cao, Liangzhi (Cao, Liangzhi.) | Wu, Hongchun (Wu, Hongchun.) (Scholars:吴宏春) | Shen, Wei (Shen, Wei.)

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SCIE EI Scopus

Abstract:

In this paper, our home-developed lattice code NECP-CACTI has been implemented into our UNICORN code to perform sensitivity and uncertainty analysis for the lattice calculations. The verified multigroup cross-section perturbation model and methods of the sensitivity and uncertainty analysis are established and applied to different lattice codes in UNICORN. As DRAGON5.0 and NECP-CACTI are available for the lattice calculations in UNICORN now, the effects of different neutronics methods (including methods for the neutron-transport and resonance self-shielding calculations) on the results of sensitivity and uncertainty analysis were studied in this paper. Based on NECP-CACTI, uncertainty analysis using the statistical sampling method has been performed to the burnup calculation for the fresh-fueled TMI-1 assembly, propagating the nuclear-data uncertainties to k(infinity) and two-group constants of the lattice calculation with depletions. As results shown, for different neutronics methods, it can be observed that different methods of the neutron-transport calculation introduce no differences to the results of sensitivity and uncertainty analysis, while different methods of the resonance self-shielding calculation would impact the results. With depletions of the TMI-1 assembly, for k(infinity), the relative uncertainty varies between 0.45% and 0.60%; for two-group constants, the largest variation is between 0.35% and 2.56% for v Sigma(f,2). Moreover, the most significant contributors to the uncertainty of k(infinity) and two-group constants varied with depletions are determined. (C) 2016 Elsevier Ltd. All rights reserved.

Keyword:

Burnup calculation Sensitivity analysis TMI-1 assembly Uncertainty analysis

Author Community:

  • [ 1 ] [Wan, Chenghui; Cao, Liangzhi; Wu, Hongchun; Shen, Wei] Xi An Jiao Tong Univ, Xian, Shaanxi, Peoples R China
  • [ 2 ] [Shen, Wei] Canadian Nucl Safety Commiss, Ottawa, ON, Canada
  • [ 3 ] [Wan, Chenghui]Xi An Jiao Tong Univ, Xian, Shaanxi, Peoples R China
  • [ 4 ] [Cao, Liangzhi]Xi An Jiao Tong Univ, Xian, Shaanxi, Peoples R China
  • [ 5 ] [Wu, Hongchun]Xi An Jiao Tong Univ, Xian, Shaanxi, Peoples R China
  • [ 6 ] [Shen, Wei]Xi An Jiao Tong Univ, Xian, Shaanxi, Peoples R China
  • [ 7 ] [Shen, Wei]Canadian Nucl Safety Commiss, Ottawa, ON, Canada

Reprint Author's Address:

  • Xi An Jiao Tong Univ, Xian, Shaanxi, Peoples R China.

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Source :

ANNALS OF NUCLEAR ENERGY

ISSN: 0306-4549

Year: 2017

Volume: 100

Page: 20-31

1 . 4 7 6

JCR@2017

1 . 7 7 6

JCR@2020

ESI Discipline: ENGINEERING;

ESI HC Threshold:121

JCR Journal Grade:2

CAS Journal Grade:2

Cited Count:

WoS CC Cited Count: 9

SCOPUS Cited Count: 11

ESI Highly Cited Papers on the List: 0 Unfold All

WanFang Cited Count:

Chinese Cited Count:

30 Days PV: 0

Affiliated Colleges:

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