Neutronic and thermal analysis of fuel rod containing light water cell in a fusion-fission hybrid reactor

被引：0

作者：

Abtahi, N. S. ^{[1
]}

Tavakoli-Anbaran, H. ^{[1
]}

Kiai, S. M. Sadat ^{[2
]}

Hassanzadeh, M. ^{[3
]}

机构：

[1] Shahrood Univ Technol, Fac Phys, POB 3619995161, Shahrood, Iran

[2] Nucl Sci & Technol Res Inst NSTRI, Plasma & Nucl Fus Res Sch, POB 14395-836, Tehran, Iran

[3] Nucl Sci & Technol Res Inst NSTRI, Reactor & Nucl Safety Sch, Tehran, Iran

来源：

ANNALS OF NUCLEAR ENERGY | 2022年 / 171卷

关键词：

Temperature feedbacks; Fusion - fission hybrid reactor; Fuel Rod; Neutronic parameters; MCNPX code; Ansys fluent; DESIGN;

D O I：

10.1016/j.anucene.2022.109043

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 most suitable diameter and pitch of fuel rods, according to neutron parameters, were determined by MCNPX code. Due to the fact that by decreasing the temperature in the fuel rod, neutron production increases in the fission process, a light water cell is created in the center of the fuel rod. The temperature reduction in the center of the fuel rod increases effective multiplication factor k(eff )and reactor's ultimate energy E-fis. Temperature changes in the light water cell and in the fuel rod are analyzed theoretically and simulated by Ansys software. Finally, the infinite multiplication factor k(infinity), k(eff), the sum of the produced neutrons in the reactor, the total released fission energy per each fusion neutron and E(fis )examined in the selected design at temperatures of 293 K, 600 K and 900 K for fuel and temperatures of 293 K and 600 K for light water cell. (C) 2022 Elsevier Ltd. All rights reserved.

引用

页数：15

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