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), 2024. Published by Science Publishing Group |
Thermal Hydraulics, Ultra High Temperature Reactor (UHTR), Pressure Drop, Porosity and Pebble Type Fuel
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| [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) |
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
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
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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Download@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}
}
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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