Nuclear design analysis of square-lattice honeycomb space nuclear rocket engine

被引:0
|
作者
Widargo, R [1 ]
Anghaie, S [1 ]
机构
[1] Univ Florida, Innovat Nucl Space Power & Prop Inst, Gainesville, FL 32611 USA
关键词
D O I
暂无
中图分类号
V [航空、航天];
学科分类号
08 ; 0825 ;
摘要
The square-lattice honeycomb reactor is designed based on a cylindrical core that is determined to have critical diameter and length of 0.50 m and 0.50 c: respectively. A 0.10-cm thick radial graphite reflector, in addition to a 0.20-m thick axial graphite reflector are used to reduce neutron leakage from the reactor. The core is fueled with solid solution of 93% enriched (U,Zr,Nb)C; which is one of several ternary uranium carbides that are considered for this concept. The fuel is to be fabricated as 2 mm grooved (U,Zr,Nb)C wafers. The fuel wafers are used to form square-lattice honeycomb fuel assemblies, 0.10 m in length with 30% cross-sectional flow area. Five fuel assemblies are stacked up axially to form the reactor core. Based on the 30% void fraction, the width of the square flow channel is about 1.3 mm. The hydrogen propellant is passed through these flow channels and removes the heat from the reactor core. To perform nuclear design analysis, a series of neutron transport and diffusion codes are used. The preliminary results are obtained using a simple four-group cross-section model. To optimize the nuclear design, the fuel densities are varied for each assembly. Tantalum, hafnium and tungsten are considered and used as a replacement for niobium in fuel material to provide water submersion sub-criticality for the reactor. Axial and radial neutron flux and power density distributions are calculated for the core. Results of the neutronic analysis indicate that the core has a relatively fast spectrum. From the results of the thermal hydraulic analyses, eight axial temperature zones are chosen for the calculation of group average cross-sections. An iterative process is conducted to couple the neutronic calculations with the thermal hydraulics calculations. Results of the nuclear design analysis indicate that a compact core can be designed based on ternary uranium carbide square-lattice honeycomb fuel. This design provides a relatively high thrust to weight ratio.
引用
收藏
页码:1507 / 1512
页数:6
相关论文
共 50 条
  • [1] Thermal hydraulic design analysis of ternary carbide fueled square-lattice honeycomb nuclear rocket engine
    Furman, EM
    Anghaie, S
    SPACE TECHNOLOGY AND APPLICATIONS INTERNATIONAL FORUM - 1999, PTS ONE AND TWO, 1999, 458 : 1501 - 1506
  • [2] DYNAMIC ANALYSIS OF A NUCLEAR ROCKET ENGINE SYSTEM
    FELIX, BR
    BOHL, RJ
    ARS JOURNAL, 1959, 29 (11): : 853 - 862
  • [3] Russian Nuclear Rocket Engine Design for Mars Exploration
    Tsinghua Space Center, School of Aerospace, Tsinghua University, Beijing, 100084, China
    不详
    Tsinghua Sci. Tech., 2007, 3 (256-260):
  • [4] Russian Nuclear Rocket Engine Design for Mars Exploration
    Vadim Zakirov
    Vladimir Pavshook
    TsinghuaScienceandTechnology, 2007, (03) : 256 - 260
  • [5] NUCLEAR ROCKET ENGINE CONTROL
    MOHLER, RR
    PERRY, JE
    NUCLEONICS, 1961, 19 (04): : 80 - &
  • [6] Design and analysis of a single stage to orbit nuclear thermal rocket reactor engine
    Labib, Satira
    King, Jeffrey
    NUCLEAR ENGINEERING AND DESIGN, 2015, 287 : 36 - 47
  • [7] STABILITY OF NUCLEAR ROCKET ENGINE DYNAMICS
    WIBERG, DM
    WOYSKI, JS
    NUCLEAR APPLICATIONS, 1968, 5 (01): : 35 - &
  • [8] GRAPHITIC FUELS FOR NUCLEAR ROCKET ENGINE
    TAUB, JM
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1975, 21 (JUN): : 173 - 174
  • [9] Experimental demonstration of waveguiding in honeycomb and square-lattice silicon photonic crystal membranes
    Puerto, Daniel
    Griol, Amadeu
    Maria Escalante, Jose
    Djafari-Rouhani, Bahram
    Pennec, Yan
    Laude, Vincent
    Beugnot, Jean-Charles
    Martinez, Alejandro
    PHOTONIC CRYSTAL MATERIALS AND DEVICES X, 2012, 8425
  • [10] System Design Selection and Parametric Optimization Analysis of 110 kN Nuclear Thermal Rocket Engine
    Wang H.
    Zuo A.
    Huo H.
    Ma X.
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2019, 53 (01): : 30 - 37