Properties and microstructures of a matrix graphite for fuel elements of pebble-bed reactors after hightemperature purification at different temperatures
Source abstract
Abstract
The matrix graphite (MG) of pebble fuel elements for a High Temperature Gas-cooled Reactor (HTGR), composed of 71wt% natural graphite, 18 wt% artificial graphite and 11 wt% phenolic resin-derived carbon, was purified by high temperature treatment (HTT), and its properties and microstructure were analyzed to investigate the effect of different HTT temperatures and optimize the purification temperature. Results showed that with increasing HTT temperature, its density and thermal conductivity gradually increased, but pore size and d002 gradually decreased. The rate of erosion caused by friction as the fuel pebbles move in the reactor also decreased. The ash content decreased significantly from to 18.2×10−6to 12.3×10−6 after HTT at 1600 °C, but changed little when the HTT temperature was further increased to 1900 °C, especially for catalytic metals such as Fe, Ni and Ca that are related to its corrosion rate. The microstructure improvement and ash content reduction at high temperatures jointly contributed to the increase in the anti-corrosion performance of MG. Based on properties such as crushing strength, erosion resistance, and corrosion rate, a HTT of 1600 °C is adequate although the MG gradually became more ordered with a further increase of HTT temperature from 1600 to 1900 °C. This determination of an appropriate HTT temperature for the production of MG for the fuel elements of an HTGR should improve the production efficiency and reduce the mass production cost of this material for a commercial HTGR.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Graphite, nuclear technology, radiation studies · Nuclear and radioactivity studies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (12)
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1. The Shandong Shidao Bay 200 MWe high-temperature gas-cooled reactor pebble-bed module (HTR-PM) demonstration power plant: An engineering and technical innovation[J]10.1016/J.ENG.2016.01.020 ↗
2. Carbon materials in a high temperature gas-cooled reactor pebble-bed module[J]10.1016/S1872-5805(18)60328-2 ↗
3. Preparation of pebble fuel elements for HTR-PM in INET[J]10.1016/j.nucengdes.2013.07.001 ↗
4. Study on the comprehensive properties and microstructures of A3-3 matrix graphite related to the high temperature purification treatment [J]10.1155/2018/6084747 ↗
5. Effects of purification on the properties and microstructures of natural flake and artificial graphite powders[J]10.1016/j.nucengdes.2020.110527 ↗
6. 2010
7. A novel approach to fabricating fuel compacts for the next generation nuclear plant (NGNP)[J]10.1016/j.jnucmat.2008.07.032 ↗
8. Windes · 2010
9. Comparison of NBG-18, NBG-17, IG-110 and IG-11 oxidation kinetics in air[J]10.1016/j.jnucmat.2017.11.053 ↗
10. Gas reactions of carbon[J]
11. Michio · 2016
12. Characterization of structural defects in nuclear graphite IG-110 and NBG-18[J]10.1016/j.jnucmat.2013.12.013 ↗