Abstract
The paper describes a problem of accumulation of irradiated graphite due to operation of uranium-graphite nuclear reactors. The main noncarbon contaminants that contribute to the overall activity of graphite elements are iso-topes 137Cs, 60Co, 90Sr, 36Cl, and 3H. A method was developed for processing of irradiated graphite ensuring the volu-metric decontamination of samples. The calculation results are presented for equilibrium composition of plasma-chemical reactions in systems “irradiated graphite−argon” and “irradiated graphite−helium” for a wide range of tem-peratures. The paper describes a developed mathematical model for the process of purification of a porous graphite surface treated by equilibrium low-temperature plasma. The simulation results are presented for the rate of sublimation of radioactive contaminants as a function of plasma temperature and plasma flow velocity when different plasma-forming gases are used. The extraction coefficient for the contaminant 137Cs from the outer side of graphite pores was calculated. The calculations demonstrated the advantages of using a lighter plasma forming gas, i.e., helium.
| Original language | English |
|---|---|
| Pages (from-to) | 109-117 |
| Number of pages | 9 |
| Journal | Thermophysics and Aeromechanics |
| Volume | 25 |
| Issue number | 1 |
| DOIs | |
| Publication status | Published - 1 Jan 2018 |
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Keywords
- decontamination
- irradiated graphite
- plasma
- processing
ASJC Scopus subject areas
- Radiation
- Nuclear and High Energy Physics
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Study of evaporating the irradiated graphite in equilibrium low-temperature plasma. / Bespala, E. V.; Novoselov, I. Yu; Pavlyuk, A. O.; Kotlyarevskiy, S. G.
In: Thermophysics and Aeromechanics, Vol. 25, No. 1, 01.01.2018, p. 109-117.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Study of evaporating the irradiated graphite in equilibrium low-temperature plasma
AU - Bespala, E. V.
AU - Novoselov, I. Yu
AU - Pavlyuk, A. O.
AU - Kotlyarevskiy, S. G.
PY - 2018/1/1
Y1 - 2018/1/1
N2 - The paper describes a problem of accumulation of irradiated graphite due to operation of uranium-graphite nuclear reactors. The main noncarbon contaminants that contribute to the overall activity of graphite elements are iso-topes 137Cs, 60Co, 90Sr, 36Cl, and 3H. A method was developed for processing of irradiated graphite ensuring the volu-metric decontamination of samples. The calculation results are presented for equilibrium composition of plasma-chemical reactions in systems “irradiated graphite−argon” and “irradiated graphite−helium” for a wide range of tem-peratures. The paper describes a developed mathematical model for the process of purification of a porous graphite surface treated by equilibrium low-temperature plasma. The simulation results are presented for the rate of sublimation of radioactive contaminants as a function of plasma temperature and plasma flow velocity when different plasma-forming gases are used. The extraction coefficient for the contaminant 137Cs from the outer side of graphite pores was calculated. The calculations demonstrated the advantages of using a lighter plasma forming gas, i.e., helium.
AB - The paper describes a problem of accumulation of irradiated graphite due to operation of uranium-graphite nuclear reactors. The main noncarbon contaminants that contribute to the overall activity of graphite elements are iso-topes 137Cs, 60Co, 90Sr, 36Cl, and 3H. A method was developed for processing of irradiated graphite ensuring the volu-metric decontamination of samples. The calculation results are presented for equilibrium composition of plasma-chemical reactions in systems “irradiated graphite−argon” and “irradiated graphite−helium” for a wide range of tem-peratures. The paper describes a developed mathematical model for the process of purification of a porous graphite surface treated by equilibrium low-temperature plasma. The simulation results are presented for the rate of sublimation of radioactive contaminants as a function of plasma temperature and plasma flow velocity when different plasma-forming gases are used. The extraction coefficient for the contaminant 137Cs from the outer side of graphite pores was calculated. The calculations demonstrated the advantages of using a lighter plasma forming gas, i.e., helium.
KW - decontamination
KW - irradiated graphite
KW - plasma
KW - processing
UR - http://www.scopus.com/inward/record.url?scp=85045389499&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85045389499&partnerID=8YFLogxK
U2 - 10.1134/S0869864318010109
DO - 10.1134/S0869864318010109
M3 - Article
AN - SCOPUS:85045389499
VL - 25
SP - 109
EP - 117
JO - Thermophysics and Aeromechanics
JF - Thermophysics and Aeromechanics
SN - 0869-8643
IS - 1
ER -