Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels

Motoo Fumizawa; Naoya Uchiyama; Takahiro Nakayama

doi:doi:10.11648/j.ijepe.20150404.11

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Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels

Motoo Fumizawa, Naoya Uchiyama, Takahiro Nakayama

Published in International Journal of Energy and Power Engineering (Volume 4, Issue 4)

Received: 29 May 2015 Accepted: 12 June 2015 Published: 1 July 2015

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Abstract

This study presents a predictive thermal-hydraulic analysis with packed spheres in a nuclear gas-cooled reactor core. The predictive analysis considering the effects of high power density and the some porosity value were applied as a design condition for an Ultra High Temperature Reactor (UHTR). The thermal-hydraulic computer code was developed and identified as PEBTEMP. The highest outlet coolant temperature of 1316 oC was achieved in the case of an UHTREX at LASL, which was a small scale UHTR using hollow-rod as a fuel element. In the present study, the fuel was changed to a pebble type, a porous media. Several calculation based on HTGR-GT300 through GT600 were 4.8 w/cm3 through 9.6 w/cm3, respectively. As a result, the relation between the fuel temperature and the power density was obtained under the different system pressure and coolant outlet temperature. Finally, available design conditions are selected.

Published in	International Journal of Energy and Power Engineering (Volume 4, Issue 4)
DOI	10.11648/j.ijepe.20150404.11
Page(s)	189-196
Creative Commons	This is an Open Access article, distributed under the terms of the Creative Commons Attribution 4.0 International License (http://creativecommons.org/licenses/by/4.0/), which permits unrestricted use, distribution and reproduction in any medium or format, provided the original work is properly cited.
Copyright	Copyright © The Author(s), 2015. Published by Science Publishing Group

Keywords

Thermal Hydraulics, Ultra High Temperature Reactor (UHTR), Pressure Drop, Porosity and Pebble Type Fuel

References

[1]	A Technology Roadmap for Generation IV Nuclear Energy Systems, GIF-002-00, Generation IV International Forum (2002), http://gif.inel.gov/roadmap/
[2]	Shusaku SHIOZAWA et al., “The HTTR Project as the World Leader of HTGR Research and Development”, J. of AESJ Vol.47, pp. 342-349 (2005)
[3]	B.M. HOGLUND,:”UHTREX Operation Near”, Vol.9, pp. 1, Power Reactor Technology (1966)
[4]	“UHTREX: Alive and Running with Coolant at 2400 oF”, Nuclear News (1969)
[5]	Progress Report – Pebble Bed Reactor Program, NYO-9071, US Atomic Energy Commission (1960)
[6]	M.M.El-Wakil, Nuclear Energy Conversion, Thomas Y. Crowell Company Inc., USA (1982)
[7]	M.M El-Wakil, Nuclear Heat Transport, International Textbook Company, USA (1971)
[8]	Motoo Fumizawa et al., “Effective Coolant Flow Rate of Flange Type Fuel Element for Very High Temperature Gas-Cooled Reactor ”, J. of AESJ Vol.31, pp 828-836 (1989)
[9]	Motoo Fumizawa et al., “Preliminary Study for Analysis of Gas-cooled Reactor with Sphere Fuel Element “, AESJ Spring MTG, I66 (2000)
[10]	Fumizawa,M.;Nuclear Reactors (ISBN 978-953-51-0967 -9), Edited by Amir Zacarias Mesquita, InTech, pp.177-191 (2013)
[11]	Motoo Fumizawa et al., “The Conceptual Design of High Temperature Engineering Test Reactor Upgraded through Utilizing Pebble-in-block Fuel”, JAERI-M 89-222 (1989)

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APA Style

Motoo Fumizawa, Naoya Uchiyama, Takahiro Nakayama. (2015). Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels. International Journal of Energy and Power Engineering, 4(4), 189-196. https://doi.org/10.11648/j.ijepe.20150404.11

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ACS Style

Motoo Fumizawa; Naoya Uchiyama; Takahiro Nakayama. Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels. Int. J. Energy Power Eng. 2015, 4(4), 189-196. doi: 10.11648/j.ijepe.20150404.11

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AMA Style

Motoo Fumizawa, Naoya Uchiyama, Takahiro Nakayama. Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels. Int J Energy Power Eng. 2015;4(4):189-196. doi: 10.11648/j.ijepe.20150404.11

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@article{10.11648/j.ijepe.20150404.11,
  author = {Motoo Fumizawa and Naoya Uchiyama and Takahiro Nakayama},
  title = {Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels},
  journal = {International Journal of Energy and Power Engineering},
  volume = {4},
  number = {4},
  pages = {189-196},
  doi = {10.11648/j.ijepe.20150404.11},
  url = {https://doi.org/10.11648/j.ijepe.20150404.11},
  eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ijepe.20150404.11},
  abstract = {This study presents a predictive thermal-hydraulic analysis with packed spheres in a nuclear gas-cooled reactor core. The predictive analysis considering the effects of high power density and the some porosity value were applied as a design condition for an Ultra High Temperature Reactor (UHTR). The thermal-hydraulic computer code was developed and identified as PEBTEMP. The highest outlet coolant temperature of 1316 oC was achieved in the case of an UHTREX at LASL, which was a small scale UHTR using hollow-rod as a fuel element. In the present study, the fuel was changed to a pebble type, a porous media. Several calculation based on HTGR-GT300 through GT600 were 4.8 w/cm3 through 9.6 w/cm3, respectively. As a result, the relation between the fuel temperature and the power density was obtained under the different system pressure and coolant outlet temperature. Finally, available design conditions are selected.},
 year = {2015}
}

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TY - JOUR
T1 - Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels
AU - Motoo Fumizawa
AU - Naoya Uchiyama
AU - Takahiro Nakayama
Y1 - 2015/07/01
PY - 2015
N1 - https://doi.org/10.11648/j.ijepe.20150404.11
DO - 10.11648/j.ijepe.20150404.11
T2 - International Journal of Energy and Power Engineering
JF - International Journal of Energy and Power Engineering
JO - International Journal of Energy and Power Engineering
SP - 189
EP - 196
PB - Science Publishing Group
SN - 2326-960X
UR - https://doi.org/10.11648/j.ijepe.20150404.11
AB - This study presents a predictive thermal-hydraulic analysis with packed spheres in a nuclear gas-cooled reactor core. The predictive analysis considering the effects of high power density and the some porosity value were applied as a design condition for an Ultra High Temperature Reactor (UHTR). The thermal-hydraulic computer code was developed and identified as PEBTEMP. The highest outlet coolant temperature of 1316 oC was achieved in the case of an UHTREX at LASL, which was a small scale UHTR using hollow-rod as a fuel element. In the present study, the fuel was changed to a pebble type, a porous media. Several calculation based on HTGR-GT300 through GT600 were 4.8 w/cm3 through 9.6 w/cm3, respectively. As a result, the relation between the fuel temperature and the power density was obtained under the different system pressure and coolant outlet temperature. Finally, available design conditions are selected.
VL - 4
IS - 4
ER -

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Author Information

Motoo Fumizawa

Department of Mechanical Engineering, Shonan Institute of Technology, Fujisawa, Kanagawa, Japan
Naoya Uchiyama

Department of Mechanical Engineering, Shonan Institute of Technology, Fujisawa, Kanagawa, Japan
Takahiro Nakayama

Department of Mechanical Engineering, Shonan Institute of Technology, Fujisawa, Kanagawa, Japan

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Plain Text BibTeX RIS

APA Style

Motoo Fumizawa, Naoya Uchiyama, Takahiro Nakayama. (2015). Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels. International Journal of Energy and Power Engineering, 4(4), 189-196. https://doi.org/10.11648/j.ijepe.20150404.11

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ACS Style

Motoo Fumizawa; Naoya Uchiyama; Takahiro Nakayama. Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels. Int. J. Energy Power Eng. 2015, 4(4), 189-196. doi: 10.11648/j.ijepe.20150404.11

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AMA Style

Motoo Fumizawa, Naoya Uchiyama, Takahiro Nakayama. Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels. Int J Energy Power Eng. 2015;4(4):189-196. doi: 10.11648/j.ijepe.20150404.11

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@article{10.11648/j.ijepe.20150404.11,
  author = {Motoo Fumizawa and Naoya Uchiyama and Takahiro Nakayama},
  title = {Thermal Analysis for an Ultra High Temperature Gas-Cooled Reactor with Pebble Type Fuels},
  journal = {International Journal of Energy and Power Engineering},
  volume = {4},
  number = {4},
  pages = {189-196},
  doi = {10.11648/j.ijepe.20150404.11},
  url = {https://doi.org/10.11648/j.ijepe.20150404.11},
  eprint = {https://article.sciencepublishinggroup.com/pdf/10.11648.j.ijepe.20150404.11},
  abstract = {This study presents a predictive thermal-hydraulic analysis with packed spheres in a nuclear gas-cooled reactor core. The predictive analysis considering the effects of high power density and the some porosity value were applied as a design condition for an Ultra High Temperature Reactor (UHTR). The thermal-hydraulic computer code was developed and identified as PEBTEMP. The highest outlet coolant temperature of 1316 oC was achieved in the case of an UHTREX at LASL, which was a small scale UHTR using hollow-rod as a fuel element. In the present study, the fuel was changed to a pebble type, a porous media. Several calculation based on HTGR-GT300 through GT600 were 4.8 w/cm3 through 9.6 w/cm3, respectively. As a result, the relation between the fuel temperature and the power density was obtained under the different system pressure and coolant outlet temperature. Finally, available design conditions are selected.},
 year = {2015}
}

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