Heat Treatment of Irradiated Graphite in an Oxidizing Atmosphere

Bespala, E. V.; Pavlyuk, A. O.; Kotlyarevskii, S. G.; Novoselov, Ivan; Bespala, Yu.R.

doi:10.3103/s0361521918050026

Cited by 2 publications

(1 citation statement)

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“…Graphite refers to difficult to combustible materials; i.e., the possibility of its burning without additional supply of energy is excluded. e temperature of the onset of intense oxidation of graphite in air is T � 450 °C [17]. In this case, oxidation will be accompanied by the release of radionuclides 14 C, 36 Cl, etc.…”

Section: Features Of Storage Of Graphite Radioactive Wastementioning

confidence: 99%

Analysis of Heat Release Processes inside Storage Facilities Containing Irradiated Nuclear Graphite

Pavliuk

Bespala²,

Kotlyarevskiy

et al. 2022

Science and Technology of Nuclear Installations

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The article is dedicated to the safety assessment of mixed storage of irradiated graphite and other types of radioactive waste accumulated during the operation of uranium-graphite reactors. The analysis of heat release processes inside storages containing irradiated nuclear graphite, representing a potential hazard due to the possible heating and, accordingly, the release of long-lived radionuclides during oxidation was carried out. The following factors were considered as the main factors that can lead to an increase in the temperature inside the storage facility: corrosion of metallic radioactive waste, the presence of fuel fragments, and also the random exposure of irradiated graphite to local sources of thermal energy (spark, etc.). It was noted in the work that the combined or separate influence of some factors can lead to an increase in the temperature of the onset of the initiation of Wigner energy release in graphite radwaste (Tin ≈ 90–100°C for the “Worst-case” graphite). The model of heat generation in the storage was developed based on the analysis of the features of graphite radioactive waste storage and Wigner energy release. The layered location of different types of waste (graphite and aluminum) and the local character of the distribution of heat sources were adopted in this model. The greatest heating is achieved if graphite radioactive waste is located near the concrete walls of the storage facility, as well as in direct contact with irradiated aluminum radioactive waste, which was shown in this paper.

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Section: Features Of Storage Of Graphite Radioactive Wastementioning

confidence: 99%