Burnup Characteristics of Transuranic Fuel With Burnable Poison in Dual Cooled Annular Rod of VVER-1000

被引:2
|
作者
Ahmed, Md. Tanvir [1 ]
Sahadath, Md. Hossain [1 ]
Islam, Md. Ashraful [1 ]
机构
[1] Univ Dhaka, Dept Nucl Engn, Dhaka 1000, Bangladesh
关键词
transuranic fuel; burnable poison; annular model; discharge burnup; cycle length; pin power; neutron flux; REACTOR; DESIGN; CORE;
D O I
10.1115/1.4055522
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 potentiality of Transuranic (TRU) fuel as dual cooled annular fuel rods with different types of burnable absorbers (BAs)- integrated burnable absorbers (IBAs), burnable poison rods (BPRs), coated absorbers, etc. in the hexagonal assembly of VVER-1000 was studied. Annular 7, Annular 8, and Annular 9 models were taken for various combinations of TRU fuel and BAs. Planned models were simulated in Monte Carlo particle simulation code OpenMC and lattice physics deterministic code Dragon Version5. Burnup-dependent multiplication factors (MFs) were simulated for 3000 effective full power days (EFPDs). Reactivity was calculated by taking 3% neutron leakage. The study showed that both the MF and reactivity for TRU fuel are significantly higher than conventional UO2 fuel. Linear reactivity model (LRM) was applied to find out cycle burnup, discharge cycle burnup, and cycle length. High cycle burnup, discharge burnup, and cycle length have been observed for TRU fuel compared to UO2 fuel. Burnup-dependent atomic concentration graphs showed that slight burn of Np-237, constant concentration for Cm-244, a slight increase for Am-242, and linear burnout of BAs- Gd-155, Gd-155, and Er-167. A lower concentration of Xe-135 has been observed for TRU fuel. Pin power distribution and energy-dependent neutron flux for different models and BAs combinations are also included in this study.
引用
收藏
页数:11
相关论文
共 50 条
  • [41] Procedure for testing VVER-1000 fuel in the MIR reactor under the conditions of an accident with ejection of a control rod
    Alekseev, A. V.
    Kiseleva, I. V.
    Ovchinnikov, V. A.
    Shulimov, V. N.
    ATOMIC ENERGY, 2006, 101 (06) : 882 - 886
  • [42] 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)
  • [43] Comparison of the results of calculations and post-reactor investigations of VVER-1000 fuel elements with burnup 49 MW•days/kg
    Passage, G.
    Stefanova, S.
    Shcheglov, A. S.
    Proselkov, V. N.
    ATOMIC ENERGY, 2006, 101 (06) : 869 - 875
  • [44] THE ANALYSIS OF INFLUENCE OF FUEL PELLET AND COOLANT TEMPERATURE DISTRIBUTIONS ON THE VVER-1000 ACTIVE CORE CHARACTERISTICS
    Mishin, A. A.
    Galchenko, V. V.
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 6, 2014,
  • [45] Neutron-physical characteristics of the upgraded VVER-1000 reactor core with fuel rods of decreased diameter
    Tchibiniaev, A
    Fomitchenko, P
    Dukhovensky, A
    Alekseev, P
    ANNUAL MEETING ON NUCLEAR TECHNOLOGY '96, 1996, : 59 - 62
  • [46] Assessment of the burnup characteristics of UO2 and MOX fuel in the mixed solid and annular rod configuration
    Akter, Yasmin
    Sahadath, Md Hossain
    Reza, Farshid
    NUCLEAR ENGINEERING AND DESIGN, 2021, 381
  • [47] Application of a Fuel-Element Energy Release Restoration Module in the ATHLET/BIPR-VVER Complex in Modeling a Control-Rod Ejection Accident in VVER-1000
    P. V. Gordienko
    A. V. Kotsarev
    M. P. Lizorkin
    V. N. Proselkov
    Atomic Energy, 2017, 122 : 15 - 18
  • [48] APPLICATION OF A FUEL-ELEMENT ENERGY RELEASE RESTORATION MODULE IN THE ATHLET/BIPR-VVER COMPLEX IN MODELING A CONTROL-ROD EJECTION ACCIDENT IN VVER-1000
    Gordienko, P. V.
    Kotsarev, A. V.
    Lizorkin, M. P.
    Proselkov, V. N.
    ATOMIC ENERGY, 2017, 122 (01) : 15 - 18
  • [49] The influence of the mechanical properties on fuel rod support characteristics - A case study of dual cooled fuel
    Kim, Jae Yong
    Kim, Hyung Kyu
    Ko, Sung Ho
    NUCLEAR ENGINEERING AND DESIGN, 2014, 275 : 53 - 60
  • [50] Influence of accounting the distribution parameters of the fuel assembly (FA) and dynamic operating characteristics on the fuel nuclide composition of a VVER-1000 spent fuel assembly (SFA)
    Albrek, M. M.
    Ternovykh, M. Y.
    Shorov, V. Y.
    INTERNATIONAL CONFERENCE FOR YOUNG SCIENTISTS, SPECIALISTS AND POST-GRADUATES ON NUCLEAR REACTOR PHYSICS, 2018, 1133