Mesoscale simulations of thermal transport in w-uo2 cermet fuel for nuclear thermal propulsion

Marina Sessim; Marvin Barnes; Robert Hickman; Michael Tonks

Mesoscale simulations of thermal transport in w-uo₂ cermet fuel for nuclear thermal propulsion

Marina Sessim
, Marvin Barnes
, Robert Hickman
, Michael Tonks

Materials Research Institute (MRI)

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

Abstract

Nuclear thermal propulsion (NTP) provides constant power for long space missions, which is a tremendous benefit over chemical rockets. Therefore, a lot of effort in investigating different fuel concepts and geometries has been invested. For applications involving NTP or nuclear power, it is very important that the heat generated by the fissile nuclei can be quickly transferred to the coolant. It is then essential that the fuel has a high thermal conductivity so that minimum stored energy is left inside the fuel. In this project, the thermal performance of a WUO₂ CERMET fuel was assessed. The effective thermal conductivity was calculated at the mesoscale for a 3-dimensional microstructure using the MOOSE framework. Then, the results were compared with published literature and analytical solutions. The thermal conductivity calculated using MOOSE was approximately 20% lower than that proposed by the Bruggeman model. The temperature profile in 7, 19 and 61-channel fuel concepts were analyzed using the MOOSE framework. The 61-channel concept had the best performance due to a better ratio of cooling surface area to fuel volume.

Original language	English (US)
Title of host publication	Nuclear and Emerging Technologies for Space, NETS 2018
Publisher	American Nuclear Society
Pages	78-81
Number of pages	4
ISBN (Print)	9781510859609
State	Published - 2016
Event	Nuclear and Emerging Technologies for Space, NETS 2018 - Las Vegas, United States Duration: Feb 26 2018 → Mar 1 2018

Publication series

Name	Nuclear and Emerging Technologies for Space, NETS 2018

Other

Other	Nuclear and Emerging Technologies for Space, NETS 2018
Country/Territory	United States
City	Las Vegas
Period	2/26/18 → 3/1/18

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 7 Affordable and Clean Energy

All Science Journal Classification (ASJC) codes

Aerospace Engineering
Renewable Energy, Sustainability and the Environment
Nuclear Energy and Engineering

Cite this

@inproceedings{3995122a324b4e019d5caa67ffd13bb4,

title = "Mesoscale simulations of thermal transport in w-uo2 cermet fuel for nuclear thermal propulsion",

abstract = "Nuclear thermal propulsion (NTP) provides constant power for long space missions, which is a tremendous benefit over chemical rockets. Therefore, a lot of effort in investigating different fuel concepts and geometries has been invested. For applications involving NTP or nuclear power, it is very important that the heat generated by the fissile nuclei can be quickly transferred to the coolant. It is then essential that the fuel has a high thermal conductivity so that minimum stored energy is left inside the fuel. In this project, the thermal performance of a WUO2 CERMET fuel was assessed. The effective thermal conductivity was calculated at the mesoscale for a 3-dimensional microstructure using the MOOSE framework. Then, the results were compared with published literature and analytical solutions. The thermal conductivity calculated using MOOSE was approximately 20\% lower than that proposed by the Bruggeman model. The temperature profile in 7, 19 and 61-channel fuel concepts were analyzed using the MOOSE framework. The 61-channel concept had the best performance due to a better ratio of cooling surface area to fuel volume.",

author = "Marina Sessim and Marvin Barnes and Robert Hickman and Michael Tonks",

note = "Publisher Copyright: {\textcopyright} 2016 American Nuclear Society. All Rights Reserved.; Nuclear and Emerging Technologies for Space, NETS 2018 ; Conference date: 26-02-2018 Through 01-03-2018",

year = "2016",

language = "English (US)",

isbn = "9781510859609",

series = "Nuclear and Emerging Technologies for Space, NETS 2018",

publisher = "American Nuclear Society",

pages = "78--81",

booktitle = "Nuclear and Emerging Technologies for Space, NETS 2018",

address = "United States",

}

Sessim, M, Barnes, M, Hickman, R & Tonks, M 2016, Mesoscale simulations of thermal transport in w-uo₂ cermet fuel for nuclear thermal propulsion. in Nuclear and Emerging Technologies for Space, NETS 2018. Nuclear and Emerging Technologies for Space, NETS 2018, American Nuclear Society, pp. 78-81, Nuclear and Emerging Technologies for Space, NETS 2018, Las Vegas, United States, 2/26/18.

Mesoscale simulations of thermal transport in w-uo₂ cermet fuel for nuclear thermal propulsion. / Sessim, Marina; Barnes, Marvin; Hickman, Robert et al.
Nuclear and Emerging Technologies for Space, NETS 2018. American Nuclear Society, 2016. p. 78-81 (Nuclear and Emerging Technologies for Space, NETS 2018).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

TY - GEN

T1 - Mesoscale simulations of thermal transport in w-uo2 cermet fuel for nuclear thermal propulsion

AU - Sessim, Marina

AU - Barnes, Marvin

AU - Hickman, Robert

AU - Tonks, Michael

PY - 2016

Y1 - 2016

N2 - Nuclear thermal propulsion (NTP) provides constant power for long space missions, which is a tremendous benefit over chemical rockets. Therefore, a lot of effort in investigating different fuel concepts and geometries has been invested. For applications involving NTP or nuclear power, it is very important that the heat generated by the fissile nuclei can be quickly transferred to the coolant. It is then essential that the fuel has a high thermal conductivity so that minimum stored energy is left inside the fuel. In this project, the thermal performance of a WUO2 CERMET fuel was assessed. The effective thermal conductivity was calculated at the mesoscale for a 3-dimensional microstructure using the MOOSE framework. Then, the results were compared with published literature and analytical solutions. The thermal conductivity calculated using MOOSE was approximately 20% lower than that proposed by the Bruggeman model. The temperature profile in 7, 19 and 61-channel fuel concepts were analyzed using the MOOSE framework. The 61-channel concept had the best performance due to a better ratio of cooling surface area to fuel volume.

AB - Nuclear thermal propulsion (NTP) provides constant power for long space missions, which is a tremendous benefit over chemical rockets. Therefore, a lot of effort in investigating different fuel concepts and geometries has been invested. For applications involving NTP or nuclear power, it is very important that the heat generated by the fissile nuclei can be quickly transferred to the coolant. It is then essential that the fuel has a high thermal conductivity so that minimum stored energy is left inside the fuel. In this project, the thermal performance of a WUO2 CERMET fuel was assessed. The effective thermal conductivity was calculated at the mesoscale for a 3-dimensional microstructure using the MOOSE framework. Then, the results were compared with published literature and analytical solutions. The thermal conductivity calculated using MOOSE was approximately 20% lower than that proposed by the Bruggeman model. The temperature profile in 7, 19 and 61-channel fuel concepts were analyzed using the MOOSE framework. The 61-channel concept had the best performance due to a better ratio of cooling surface area to fuel volume.

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M3 - Conference contribution

AN - SCOPUS:85051995329

SN - 9781510859609

T3 - Nuclear and Emerging Technologies for Space, NETS 2018

SP - 78

EP - 81

BT - Nuclear and Emerging Technologies for Space, NETS 2018

PB - American Nuclear Society

T2 - Nuclear and Emerging Technologies for Space, NETS 2018

Y2 - 26 February 2018 through 1 March 2018

ER -