|Table of Contents|

Effective thermal conductivity model applied in pellet bed reactors for nuclear thermal propulsion(PDF)

《火箭推进》[ISSN:1672-9374/CN:CN 61-1436/V]

Issue:
2024年04期
Page:
94-102
Research Field:
目次
Publishing date:

Info

Title:
Effective thermal conductivity model applied in pellet bed reactors for nuclear thermal propulsion
Author(s):
YOU Ersheng1 LI Yiyi1 WANG Tianmi1 XING Dianchuan1 JI Yu2 XU Jianjun1
1. CNNC Key Laboratory of Nuclear Reactor Thermal Hydraulics Technology,Nuclear Power Institute of China(NPIC), Chengdu 610213, China; 2. Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China
Keywords:
effective thermal conductivity model application pellet bed reactors nuclear thermal propulsion
PACS:
TL99
DOI:
10.3969/j.issn.1672-9374.2024.04.009
Abstract:
Nuclear thermal propulsion(NTP)is a new-type nuclear reactor application which chooses hydrogen gas as the working medium, heated by fuel pellets in the reactor core to extremely high temperature, so as to achieve huge thrust and high specific impulse. Based on the typical design of reactor core in American NTP rocket engine programs, the effective thermal conductivity model of high temperature gas-cooled reactors was used and preliminary applied, for the analysis of the pellet bed mixed with smaller fuel particles and higher temperature hydrogen gas. The influences of fuel type, pellet diameter and pellet bed porosity on the thermal conductivity of the reactor core were also obtained in this paper. Meanwhile, considering that the fuel pellet was usually coated by multi-layers with different materials, the homogenization method was used for equivalent calculation in thermal properties of these materials, aimed to provide the average thermal conductivity parameters of solid domain for the effective thermal conductivity model. According to the calculation results, the pellet diameter and pellet bed porosity have a greater impact on the effective thermal conductivity, relative to the components thermal conductivity, especially under high temperature conditions that the radiation heat transfer is dominant.

References:

[1] 张泽, 薛翔, 王园丁, 等. 空间核动力推进技术研究展望[J]. 火箭推进, 2021, 47(5): 1-13.
ZHANG Z, XUE X, WANG Y D, et al. Prospect of space nuclear power propulsion technology[J]. Journal of Rocket Propulsion, 2021, 47(5): 1-13.
[2]游尔胜, 石磊, 郑艳华, 等. 球床堆在空间核动力系统中的应用[J]. 原子能科学技术, 2015, 49(S1): 75-80.
YOU E S, SHI L, ZHENG Y H, et al. Application of pellet bed reactor in space nuclear power system[J]. Atomic Energy Science and Technology, 2015, 49(S1): 75-80.
[3]IAEA. The role of nuclear power and nuclear propulsion in the peaceful exploration of space[R]. Vienna: International Atomic Energy Agency, 2005.
[4]ROBBINS W. An historical perspective of the NERVA nuclear rocket engine technology program[C]//Conference on Advanced SEI Technologies. Reston, Virginia: AIAA, 1991.
[5]FINSETH J L. Overview of ROVER engine tests final report[R]. Huntsville, AL: Marshall Space Flight Center, 1991.
[6]PONOMAREV-STEPNOI N N, KUKHARKIN N E, USOV V A. Russian space nuclear power and nuclear thermal propulsion systems[J]. Nuclear News, 2000, 76(13): 37-46.
[7]ASKER J R. Particle bed reactor central to SDI nuclear rocket project[J]. Aviation Week and Space Technology, 1991, 134: 18-25.
[8]POWELL J, MAISE G, PANIAGUA J. Pluto orbiter/lander/sample return missions using the MITEE nuclear engine[C]//Aerospace Conference. Big Sky, MT: IEEE, 2003.
[9]EI-GENK M S, MORLEY N J, HALOULAKOS V E B. Pellet bed reactor for nuclear thermal propelled vehicles[Z]. 1991.
[10]EL-GENK M S. Deployment history and design considerations for space reactor power systems[J]. Acta Astronautica, 2009, 64(9): 833-849.
[11]SCHRIENER T M, EL-GENK M S. Effects of decreasing fuel enrichment on the design of the Pellet Bed Reactor(PeBR)for lunar outposts[J]. Progress in Nuclear Energy, 2018, 104: 288-297.
[12]游尔胜, 佘顶, 陈福冰, 等. 小型化气冷球床堆方案设计与应用研究[J]. 原子能科学技术, 2017, 51(7): 1167-1172.
YOU E S, SHE D, CHEN F B, et al. Conceptual design and application research on small gas-cooled pebble bed reactor[J]. Atomic Energy Science and Technology, 2017, 51(7): 1167-1172.
[13]吉宇, 毛晨瑞, 孙俊, 等. 核热火箭发动机系统循环方案分析与设计[J]. 火箭推进, 2022, 48(1): 14-21.
JI Y, MAO C R, SUN J, et al. Analysis and design of system cycle for nuclear thermal rocket engine[J]. Journal of Rocket Propulsion, 2022, 48(1): 14-21.
[14]王浩泽, 左安军, 霍红磊, 等. 110 kN核热火箭发动机系统方案选取与参数优化研究[J]. 原子能科学技术, 2019, 53(1): 30-37.
WANG H Z, ZUO A J, HUO H L, et al. System design selection and parametric optimization analysis of 110 kN nuclear thermal rocket engine[J]. Atomic Energy Science and Technology, 2019, 53(1): 30-37.
[15]SELCOW E C, DAVIS R E, PERKINS K R, et al. Assessment of the use of H2, CH4, NH3 and CO2 as NTR propellants[C]//AIP Conference. Albuquerque: AIP, 1992.
[16]ASSAEL M J, ASSAEL J, HUBER M L, et al. Correlation of the thermal conductivity of normal and parahydrogen from the triple point to 1 000 K and up to 100 MPa[J]. Journal of Physical and Chemical Reference Data, 2011, 40(3): 33-101.
[17]BAUER R, SCHLUNDER E U. Effective radial thermal conductivity of packings in gas flow[J]. International Chemical Engineering, 1978, 18(2): 181-204.
[18]YOU E S, SUN X M, CHEN F B, et al. An improved prediction model for the effective thermal conductivity of compact pebble bed reactors[J]. Nuclear Engineering and Design, 2017, 323: 95-102.

Memo

Memo:
-
Last Update: 1900-01-01