Criticality and burnup analyses of a PBMR-400 full core using Monte Carlo calculation method

被引：15
|
作者：
Acir, Adem [1 ]
Coskun, Hasan [2 ]
Sahin, Haci Mehmet [1 ]
Erol, Ozgur [3 ]
机构：
[1] Gazi Univ, Tech Educ Fac, Div Energy, Ankara, Turkey
[2] Gazi Univ, Inst Sci & Technol, Ankara, Turkey
[3] Baskent Univ, Fac Engn, Dept Mech Engn, TR-06490 Ankara, Turkey
来源：
ANNALS OF NUCLEAR ENERGY | 2011年 / 38卷 / 2-3期
关键词：
Monte Carlo; MONTEBURNS; PBMR-400; Criticality; Burnup analysis; Packing fraction;
D O I：
10.1016/j.anucene.2010.10.013
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, the criticality and burnup analyses have been performed for full core model of Pebble Bed Modular Reactors, such as PBMR-400, using the computer codes MCNP5.1.4 and MONTEBURNS 2.0. Three different pebble distributions, namely: Body Centered Cubic (BCC) (packing fraction = 68%), Random Packing (RP) (packing fraction = 61%) and Simple Cubic (SC) (packing fraction = 52%) were selected for the analyses. The calculated core effective multiplication factor, k(eff), for BCC, RP and SC came to be 1.2395, 1.2357 and 1.2223, respectively. The core life for these distributions were calculated as similar to 1200, 1000, and 800 Effective Full Power Days (EFPDs), whereas, the corresponding burnups came out to be similar to 99,000, similar to 92,000 and similar to 86,000 MWD/T, respectively, for end of life k(eff) set equal to 1.02. (C) 2010 Elsevier Ltd. All rights reserved.
引用
收藏
页码：298 / 301
页数：4
相关论文
共 50 条
  • [21] Calculation of radial burnup and nuclides atom density distributions in a VVER-1000 fuel rod using Monte Carlo method
    Pirouzmand, Ahmad
    Roosta, Fatemeh
    [J]. PROGRESS IN NUCLEAR ENERGY, 2016, 88 : 321 - 331
  • [22] Determination of burnup limit for CANDU 6 fuel using Monte-Carlo method
    Lee, Eun-ki
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2021, 53 (03) : 901 - 910
  • [23] 2D full-core Monte Carlo pin-by-pin burnup calculations with the RMC code
    She, Ding
    Liang, Jingang
    Wang, Kan
    Forget, Benoit
    [J]. ANNALS OF NUCLEAR ENERGY, 2014, 64 : 201 - 205
  • [24] Domain Decomposition Strategy for Pin-wise Full-Core Monte Carlo Depletion Calculation with the Reactor Monte Carlo Code
    Liang, Jingang
    Wang, Kan
    Qiu, Yishu
    Chai, Xiaoming
    Qiang, Shenglong
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2016, 48 (03) : 635 - 641
  • [25] CORE BURNUP CALCULATION METHOD FOR SPECTRAL SHIFT REACTOR USING FERTILE ROD
    OKUMURA, K
    ISHIGURO, Y
    KANEKO, K
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1988, 25 (12) : 948 - 951
  • [26] Criticality evaluation considering nonuniformity effect using Monte Carlo perturbation method
    Shiba, Shigeki
    Sakai, Tomohiro
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2023, 60 (08) : 943 - 954
  • [27] Study of Dose Calculation Using Monte Carlo Method in Radiotherapy
    Gao, C.
    Chi, Z.
    Liu, D.
    [J]. MEDICAL PHYSICS, 2013, 40 (06)
  • [28] Fast fission factor calculation using Monte Carlo method
    Arkani, M.
    Khalafi, H.
    Eskandari, M. R.
    [J]. PROGRESS IN NUCLEAR ENERGY, 2012, 54 (01) : 167 - 170
  • [29] A new direct calculation method of response matrices using a Monte Carlo calculation
    Moriwaki, M
    Ishii, K
    Maruyama, H
    Aoyama, M
    [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1999, 36 (10) : 877 - 887
  • [30] Real Variance Estimation in Monte Carlo Criticality Calculation Accelerated by p-CMFD Feedback Using Spectral Analysis Method
    Kim, HyeonTae
    Jo, YuGwon
    Kim, Yonghee
    [J]. NUCLEAR SCIENCE AND ENGINEERING, 2020, 194 (04) : 297 - 307
12345