Preliminary Study of a Prismatic-Core Advanced High-Temperature Reactor Fuel Using Homogenization Double-Heterogeneous Method

Mohammad Alrwashdeh; Saeed A. Alameri; Ahmed K. Alkaabi

doi:10.1080/00295639.2019.1672511

Preliminary Study of a Prismatic-Core Advanced High-Temperature Reactor Fuel Using Homogenization Double-Heterogeneous Method

Mohammad Alrwashdeh, Saeed A. Alameri, Ahmed K. Alkaabi

Research output: Contribution to journal › Article › peer-review

36 Scopus citations

Abstract

The double heterogeneity of the tristructural isotropic (TRISO) fuel in the prismatic-core advanced high-temperature reactor should be accurately and correctly modeled and analyzed, especially for a large-scale loaded with the double-heterogeneity effect. The reactivity-equivalent physical transformation method was developed and employed to enable homogenizing TRISO fuel in a high temperature reactor considering the double heterogeneity and taking into account the large problem involved in performing the whole-core burnup calculation using Monte Carlo transport codes with double-heterogeneity problems. In this work, the heterogeneous effects of a collision of probability calculation method were used to represent the effects of scattering anisotropy on the leakage rates and the isotropic streaming effects due to low optical density in the model. The WIMS and DRAGON codes have been used to perform the calculations of double heterogeneity for the TRISO fuel, fuel compact, and fuel element and the results are compared with the SERPENT Monte Carlo code.

Original language	British English
Pages (from-to)	163-167
Number of pages	5
Journal	Nuclear Science and Engineering
Volume	194
Issue number	2
DOIs	https://doi.org/10.1080/00295639.2019.1672511
State	Published - 1 Feb 2020

Keywords

high-temperature reactor
Monte Carlo
TRISO fuel

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10.1080/00295639.2019.1672511

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title = "Preliminary Study of a Prismatic-Core Advanced High-Temperature Reactor Fuel Using Homogenization Double-Heterogeneous Method",

abstract = "The double heterogeneity of the tristructural isotropic (TRISO) fuel in the prismatic-core advanced high-temperature reactor should be accurately and correctly modeled and analyzed, especially for a large-scale loaded with the double-heterogeneity effect. The reactivity-equivalent physical transformation method was developed and employed to enable homogenizing TRISO fuel in a high temperature reactor considering the double heterogeneity and taking into account the large problem involved in performing the whole-core burnup calculation using Monte Carlo transport codes with double-heterogeneity problems. In this work, the heterogeneous effects of a collision of probability calculation method were used to represent the effects of scattering anisotropy on the leakage rates and the isotropic streaming effects due to low optical density in the model. The WIMS and DRAGON codes have been used to perform the calculations of double heterogeneity for the TRISO fuel, fuel compact, and fuel element and the results are compared with the SERPENT Monte Carlo code.",

keywords = "high-temperature reactor, Monte Carlo, TRISO fuel",

author = "Mohammad Alrwashdeh and Alameri, {Saeed A.} and Alkaabi, {Ahmed K.}",

note = "Funding Information: This study was supported by the Khalifa University of Science and Technology Faculty Start-Up Fund, FSU 8474000067. Funding Information: This study was supported by the Khalifa University of Science and Technology Faculty Start-Up Fund, FSU 8474000067. Publisher Copyright: {\textcopyright} 2019, {\textcopyright} 2019 American Nuclear Society.",

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N1 - Funding Information: This study was supported by the Khalifa University of Science and Technology Faculty Start-Up Fund, FSU 8474000067. Funding Information: This study was supported by the Khalifa University of Science and Technology Faculty Start-Up Fund, FSU 8474000067. Publisher Copyright: © 2019, © 2019 American Nuclear Society.

PY - 2020/2/1

Y1 - 2020/2/1

N2 - The double heterogeneity of the tristructural isotropic (TRISO) fuel in the prismatic-core advanced high-temperature reactor should be accurately and correctly modeled and analyzed, especially for a large-scale loaded with the double-heterogeneity effect. The reactivity-equivalent physical transformation method was developed and employed to enable homogenizing TRISO fuel in a high temperature reactor considering the double heterogeneity and taking into account the large problem involved in performing the whole-core burnup calculation using Monte Carlo transport codes with double-heterogeneity problems. In this work, the heterogeneous effects of a collision of probability calculation method were used to represent the effects of scattering anisotropy on the leakage rates and the isotropic streaming effects due to low optical density in the model. The WIMS and DRAGON codes have been used to perform the calculations of double heterogeneity for the TRISO fuel, fuel compact, and fuel element and the results are compared with the SERPENT Monte Carlo code.

AB - The double heterogeneity of the tristructural isotropic (TRISO) fuel in the prismatic-core advanced high-temperature reactor should be accurately and correctly modeled and analyzed, especially for a large-scale loaded with the double-heterogeneity effect. The reactivity-equivalent physical transformation method was developed and employed to enable homogenizing TRISO fuel in a high temperature reactor considering the double heterogeneity and taking into account the large problem involved in performing the whole-core burnup calculation using Monte Carlo transport codes with double-heterogeneity problems. In this work, the heterogeneous effects of a collision of probability calculation method were used to represent the effects of scattering anisotropy on the leakage rates and the isotropic streaming effects due to low optical density in the model. The WIMS and DRAGON codes have been used to perform the calculations of double heterogeneity for the TRISO fuel, fuel compact, and fuel element and the results are compared with the SERPENT Monte Carlo code.

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Preliminary Study of a Prismatic-Core Advanced High-Temperature Reactor Fuel Using Homogenization Double-Heterogeneous Method

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