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Graphite Testing for Nuclear Applications: The Validity and Extension of Test Methods for Material Exposed to Operating Reactor EnvironmentsAvailable to Purchase
Editor
Athanasia Tzelepi,
Athanasia Tzelepi
Symposium Co-Chair and STP Editor
1
National Nuclear Laboratory
, Sellafield,
GB
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Martin Metcalfe
Martin Metcalfe
Symposium Co-Chair and STP Editor
2
Nuclear Graphite Research Group, Nuclear Engineering Department of MACE, University of Manchester
, Manchester,
GB
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ISBN:
978-0-8031-7725-3
No. of Pages:
312
Publisher:
ASTM International
Publication date:
2022
eBook Chapter
Testing Methods for Graphite Exposed to Molten Salt Reactor Environment Available to Purchase
By
Dongbo Xiong
,
Dongbo Xiong
1
Shanghai Institute of Applied Physics, Chinese Academy of Sciences
, 2019 Jialuo Rd., Shanghai,
CN
2018002
University of Chinese Academy of Sciences
, 19(A) Yuquan Rd., Beijing,
CN
100049
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Derek Tsang
Derek Tsang
1
Shanghai Institute of Applied Physics, Chinese Academy of Sciences
, 2019 Jialuo Rd., Shanghai,
CN
201800
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Page Count:
18
-
Published:2022
Citation
Xiong, D, & Tsang, D. "Testing Methods for Graphite Exposed to Molten Salt Reactor Environment." Graphite Testing for Nuclear Applications: The Validity and Extension of Test Methods for Material Exposed to Operating Reactor Environments. Ed. Tzelepi, A, & Metcalfe, M. 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959 : ASTM International, 2022.
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As one of the preferred designs in Generation IV reactors, the molten salt reactor (MSR) is gaining a lot of interest around the world. The MSR uses molten salt as a coolant to transfer heat out from its reactor core. Components of the MSR would be inevitably damaged by both irradiation and molten salt erosion. Nuclear graphite, as a moderator and reflector for the MSR, may receive more irradiation dose than other nuclear materials inside the reactor core. Graphite is also a porous material, and impregnation of molten salts may cause damage to its internal structure. Moreover, the effects of molten salt impregnation are more uncertain due to the change of material properties by irradiation. Here, potential problems in using graphite in the MSR are reviewed. Experimental methods for nuclear graphite exposed to a molten salt environment are also discussed.
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