Neutronic and fuel cycle performance of VVER-1000 for dual cooled annular fuel with coated burnable poison

被引:19
|
作者
Hossain, Md Towhid [1 ]
Sahadath, Md Hossain [1 ]
Nabila, Umme Mahbuba [1 ]
机构
[1] Univ Dhaka, Dept Nucl Engn, Dhaka 1000, Bangladesh
关键词
VVER-1000; Dual cooled; Coated poison; Neutronics; Fuel cycle; DESIGN;
D O I
10.1016/j.pnucene.2022.104139
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 feasibility of the dual cooled annular fuel rod with coated burnable absorber in the hexagonal assembly of the VVER-1000 reactor was studied. The models consist of a 4.5% enriched dual cooled UO2 fuel rod with a coating of Gd2O3, Er2O3, PaO2, AmO2, and ZrB2 as the burnable absorber. Designed models along with the reference designs were simulated in lattice physics code Dragon and Monte Carlo code OpenMC. Burnup analysis was conducted for 1620 EFPD. The multiplication factor, as well as reactivity, was determined for fuel burnup. Improvement in the multiplication factor and reactivity is observed for dual cooled annular fuel with coated burnable poison. Designed models also showed a significant increase in thermal fission reaction rate compared to the reference design. Linear reactivity model (LRM) was used to calculate cycle burnup, discharge burnup, and cycle length for three and four batch refueling schemes. No degradation is observed in fuel cycle performance using dual cooled annular fuel with coated burnable absorber except for the model of gadolinium. The other absorbers showed better results than gadolinium in both neutronic and fuel cycle performance. PaO2 used model showed the most promising result among them. The value of k-infinity was found to be 1.27089 at BOL and the cycle burnup was around 15 MWD/kg. Also, no cycle length penalty was observed for PaO2. Burnup-dependent atomic concentration was studied. A lower concentration of fission product poison was also noticed in designed models. The analysis of relative pin power distribution and energy-dependent neutron flux is also included in this study.
引用
收藏
页数:10
相关论文
共 50 条
  • [21] Fuel management for VVER-1000 using PC fuel
    Xu, Min
    Wang, Hongxia
    Huo, Xiaodong
    Yi, Xuan
    Yu, Yang
    Hedongli Gongcheng/Nuclear Power Engineering, 2015, 36 (04): : 37 - 40
  • [22] Analysis of VVER-1000 fuel cycle using MCNPX code
    Huml, Ondrej
    PROCEEDINGS OF THE 13TH INTERNATIONAL SCIENTIFIC CONFERENCE ELECTRIC POWER ENGINEERING 2012, VOLS 1 AND 2, 2012, : 1235 - 1239
  • [23] Investigation of Neutronic and Thermal Performance Using UGD and MOX Fuel in VVER-1000 Nuclear Power Reactor
    Uzun, Sinem
    Genc, Yasin
    Acir, Adem
    JOURNAL OF POLYTECHNIC-POLITEKNIK DERGISI, 2021, 24 (04): : 1557 - 1565
  • [24] Optimal design of a VVER-1000 nuclear reactor core with dual cooled annular fuel based on the reactivity temperature coefficients using Thermal hydraulic and neutronic analysis by implementing the genetic algorithms
    Kianpour, R.
    Ansarifar, G. R.
    Fathi, M.
    ANNALS OF NUCLEAR ENERGY, 2020, 148 (148)
  • [25] Calculational benchmark problems for VVER-1000 mixed oxide fuel cycle
    Emmett, MB
    PROCEEDINGS OF THE TOPICAL MEETING ON RADIATION PROTECTION FOR OUR NATIONAL PRIORITIES: MEDICINE, THE ENVIRONMENT, AND THE LEGACY, 2000, : 248 - 251
  • [26] The choice of the fuel assembly for VVER-1000 in a closed fuel cycle based on REMIX-technology
    Bobrov, Evgenii
    Alekseev, Pavel
    Chibinyaev, Alexander
    Teplov, Pavel
    Dudnikov, Anatoliy
    EPJ NUCLEAR SCIENCES & TECHNOLOGIES, 2016, 2
  • [27] Fuel utilization in VVER-1000: Status and prospects
    Lunin, G. L.
    Novikov, A. N.
    Pavlov, V. I.
    Pavlovichev, A. M.
    Semchenkov, Yu. M.
    Spirkin, E. I.
    Kosourov, E. K.
    ATOMIC ENERGY, 2007, 102 (03) : 165 - 173
  • [28] Thermal hydraulic analysis of VVER-1000 nuclear reactor with dual-cooled annular fuel using K-ω SST Turbulence model
    Zaidabadi, M.
    Ansarifar, G. R.
    Esteki, M. H.
    ANNALS OF NUCLEAR ENERGY, 2017, 101 : 118 - 127
  • [29] Uranium Oxide Fuel Cycle Analysis in VVER-1000 with VISTA Simulation Code
    Mirekhtiary, Seyedeh Fatemeh
    Abbasi, Akbar
    TURKISH PHYSICAL SOCIETY 33RD INTERNATIONAL PHYSICS CONGRESS (TPS33), 2018, 1935
  • [30] Equilibrium Thorium Fuel Loading in VVER-1000 Reactor
    Frybort, Jan
    PROCCEDINGS OF THE 2014 15TH INTERNATIONAL SCIENTIFIC CONFERENCE ON ELECTRIC POWER ENGINEERING (EPE), 2014,