Experimental study to estimate the surface wear of nuclear graphite in HTR-PM

Xiujie He; Li Shi; Haiyan Li; Jie Tan; Baoliang Zhang; Alex Fok; Xinxin Wu; Libin Sun

doi:10.1016/j.anucene.2018.02.046

Experimental study to estimate the surface wear of nuclear graphite in HTR-PM

Xiujie He, Li Shi, Haiyan Li, Jie Tan, Baoliang Zhang, Alex Fok, Xinxin Wu, Libin Sun

Biomaterials

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

6 Scopus citations

Abstract

The aim of this study was to simulate the surface wear of graphite components in a pebble-bed nuclear reactor caused by the moving fuel balls and, thus, to help evaluate the integrity of the whole graphite structures over their service life. To this end, wear tests were conducted on the chewing machine with a specially designed load jig. The test specimens included graphite plates and graphite spheres, to represent the graphite bricks and fuel spheres, respectively. The main parameters, including volume loss of graphite plates and spheres, micro-morphology of the wear surface and weight and particle size of graphite dust generated, were studied in this work.

Original language	English (US)
Pages (from-to)	296-302
Number of pages	7
Journal	Annals of Nuclear Energy
Volume	116
DOIs	https://doi.org/10.1016/j.anucene.2018.02.046
State	Published - Jun 2018

Bibliographical note

Funding Information:
This work is supported by the National Natural Science Foundation of China ( 11502130 ) and the National S&T Major Project (ZX06901).

Keywords

High temperature gas-cooled reactor
Nuclear graphite
Pebble-bed
Surface wear

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10.1016/j.anucene.2018.02.046

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title = "Experimental study to estimate the surface wear of nuclear graphite in HTR-PM",

abstract = "The aim of this study was to simulate the surface wear of graphite components in a pebble-bed nuclear reactor caused by the moving fuel balls and, thus, to help evaluate the integrity of the whole graphite structures over their service life. To this end, wear tests were conducted on the chewing machine with a specially designed load jig. The test specimens included graphite plates and graphite spheres, to represent the graphite bricks and fuel spheres, respectively. The main parameters, including volume loss of graphite plates and spheres, micro-morphology of the wear surface and weight and particle size of graphite dust generated, were studied in this work.",

keywords = "High temperature gas-cooled reactor, Nuclear graphite, Pebble-bed, Surface wear",

author = "Xiujie He and Li Shi and Haiyan Li and Jie Tan and Baoliang Zhang and Alex Fok and Xinxin Wu and Libin Sun",

note = "Funding Information: This work is supported by the National Natural Science Foundation of China ( 11502130 ) and the National S&T Major Project (ZX06901). ",

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doi = "10.1016/j.anucene.2018.02.046",

language = "English (US)",

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T1 - Experimental study to estimate the surface wear of nuclear graphite in HTR-PM

AU - He, Xiujie

AU - Shi, Li

AU - Li, Haiyan

AU - Tan, Jie

AU - Zhang, Baoliang

AU - Fok, Alex

AU - Wu, Xinxin

AU - Sun, Libin

N1 - Funding Information: This work is supported by the National Natural Science Foundation of China ( 11502130 ) and the National S&T Major Project (ZX06901).

PY - 2018/6

Y1 - 2018/6

N2 - The aim of this study was to simulate the surface wear of graphite components in a pebble-bed nuclear reactor caused by the moving fuel balls and, thus, to help evaluate the integrity of the whole graphite structures over their service life. To this end, wear tests were conducted on the chewing machine with a specially designed load jig. The test specimens included graphite plates and graphite spheres, to represent the graphite bricks and fuel spheres, respectively. The main parameters, including volume loss of graphite plates and spheres, micro-morphology of the wear surface and weight and particle size of graphite dust generated, were studied in this work.

AB - The aim of this study was to simulate the surface wear of graphite components in a pebble-bed nuclear reactor caused by the moving fuel balls and, thus, to help evaluate the integrity of the whole graphite structures over their service life. To this end, wear tests were conducted on the chewing machine with a specially designed load jig. The test specimens included graphite plates and graphite spheres, to represent the graphite bricks and fuel spheres, respectively. The main parameters, including volume loss of graphite plates and spheres, micro-morphology of the wear surface and weight and particle size of graphite dust generated, were studied in this work.

KW - High temperature gas-cooled reactor

KW - Nuclear graphite

KW - Pebble-bed

KW - Surface wear

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DO - 10.1016/j.anucene.2018.02.046

M3 - Article

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SN - 0306-4549

VL - 116

SP - 296

EP - 302

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

ER -

Experimental study to estimate the surface wear of nuclear graphite in HTR-PM

Abstract

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Keywords

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