Application of Monte Carlo Method for Burnup Dependent Full Core Neutronic Analysis of PBMR

被引：0
|
作者：
Tombakoglu, Mehmet [1 ]
Celik, Cihangir [1 ,2 ]
机构：
[1] Hacettepe Univ, Dept Nucl Engn, TR-06800 Ankara, Turkey
[2] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
来源：
24TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2015) | 2015年
关键词：
D O I：
暂无
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：
In this study, computational results of burnup dependent full core neutronic analysis of Pebble Bed Modular Reactor (PBMR) are presented. The calculations were performed by the MCNP-4b and BURN-HUNEM codes. BURN-HUNEM code was developed and utilized to perform depletion calculations using the cross section data generated by MCNP-4b to include double heterogeneity effect on neutronic parameters. The results for equilibrium cycle core composition and burnup were presented for once-through-then-out (OTTO) and Mehrfach-DUrchLauf (MEDUL) i.e., multi-pass, fuel cycle strategies.
引用
收藏
页数：6
相关论文
共 50 条
  • [1] Criticality and burnup analyses of a PBMR-400 full core using Monte Carlo calculation method
    Acir, Adem
    Coskun, Hasan
    Sahin, Haci Mehmet
    Erol, Ozgur
    [J]. ANNALS OF NUCLEAR ENERGY, 2011, 38 (2-3) : 298 - 301
  • [2] Data decomposition method for full-core Monte Carlo transport–burnup calculation
    Hong-Fei Liu
    Peng Ge
    Sheng-Peng Yu
    Jing Song
    Xiao-Lei Zheng
    [J]. Nuclear Science and Techniques, 2018, 29 (02) : 99 - 106
  • [3] Data decomposition method for full-core Monte Carlo transport–burnup calculation
    Hong-Fei Liu
    Peng Ge
    Sheng-Peng Yu
    Jing Song
    Xiao-Lei Zheng
    [J]. Nuclear Science and Techniques, 2018, 29
  • [4] Data decomposition method for full-core Monte Carlo transport-burnup calculation
    Liu, Hong-Fei
    Ge, Peng
    Yu, Sheng-Peng
    Song, Jing
    Zheng, Xiao-Lei
    [J]. NUCLEAR SCIENCE AND TECHNIQUES, 2018, 29 (02)
  • [5] Neutronic analysis of the PBMR-400 full core using thorium fuel mixed with plutonium or minor actinides
    Acir, Adem
    Coskun, Hasan
    [J]. ANNALS OF NUCLEAR ENERGY, 2012, 48 : 45 - 50
  • [6] Calculation of time-dependent neutronic parameters using Monte Carlo method
    Shayesteh, M.
    Shahriari, M.
    [J]. ANNALS OF NUCLEAR ENERGY, 2009, 36 (07) : 901 - 909
  • [7] Coupled neutronic thermo-hydraulic analysis of full PWR core with Monte-Carlo based BGCore system
    Kotlyar, D.
    Shaposhnik, Y.
    Fridman, E.
    Shwageraus, E.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (09) : 3777 - 3786
  • [8] Neutronic Analysis of Ventilated Dry Storage Cask with Monte Carlo Method
    Sarioglu, Burak
    Lule, Senem Senturk
    Colak, Uner
    [J]. 30TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2021), 2021,
  • [9] Application of Monte Carlo Method in Tolerance Analysis
    Yan, Huiwen
    Wu, Xiangji
    Yang, Jiangxin
    [J]. 13TH CIRP CONFERENCE ON COMPUTER AIDED TOLERANCING, 2015, 27 : 281 - 285
  • [10] NEUTRONIC ANALYSIS CODE FOR FUEL ASSEMBLY USING A VECTORIZED MONTE-CARLO METHOD
    MORIMOTO, Y
    MARUYAMA, H
    ISHII, K
    AOYAMA, M
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 1989, 103 (04) : 351 - 358
12345