A mathematical model for the release of noble gas and Cs from porous nuclear fuel based on VEGA 1&amp;2 experiments

Simones, Matthew P.; Reinig, Michael L.; Loyalka, Sudarshan K.

doi:10.1016/j.jnucmat.2014.01.050

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Appendix A: the Infusion Profile Of Cs In Nbg-181

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“…We also note that in Ref. [19] a numerical technique was applied to compute time dependent fission product release from irradiated nuclear fuels heated at increasing temperatures (temperature ramp) in a furnace at very high temperatures. This technique would be suitable for further analysis of the infusion part also and coupling of the time dependent infusion chamber Cs concentration with the Cs concentration in the graphite sphere.…”

Section: Appendix A: the Infusion Profile Of Cs In Nbg-18mentioning

confidence: 99%

ICP-MS measurement of diffusion coefficients of Cs in NBG-18 graphite

Carter

Brockman

Robertson

et al. 2015

Journal of Nuclear Materials

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Graphite is used in the HGTR/VHTR as moderator and it also functions as a barrier to fission product release. Therefore, an elucidation of transport of fission products in reactor-grade graphite is required. We have measured diffusion coefficients of Cs in graphite NBG-18 using the release method, wherein we infused spheres of NBG-18 with Cs and measured the release rates in the temperature range of 1090-1395 K. We have obtained:

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Section: Appendix A: the Infusion Profile Of Cs In Nbg-18mentioning

confidence: 99%