Abstract
The article focuses on discussion of problem of graphite radioactive waste formation and accumulation. It is shown that irradiated nuclear graphite being inalienable part of uranium-graphite reactor may contain fission and activation products. Much attention is given to the process of formation of radioactive cesium on the graphite element surface. It is described a process of plasma decontamination of irradiated graphite in inert argon atmosphere. Quasi-one mathematical model is offered, it describes heat transfer process in graphite-cesium-argon system. Article shows results of calculation of temperature field inside the unit cell. Authors determined the factors which influence on temperature change.
| Original language | English |
|---|---|
| Article number | 01011 |
| Journal | MATEC Web of Conferences |
| Volume | 72 |
| DOIs | |
| Publication status | Published - 9 Aug 2016 |
| Event | Heat and Mass Transfer in the System of Thermal Modes of Energy - Technical and Technological Equipment, HMTTSC 2016 - Tomsk, Russian Federation Duration: 19 Apr 2016 → 21 Apr 2016 |
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ASJC Scopus subject areas
- Chemistry(all)
- Engineering(all)
- Materials Science(all)
Cite this
Heat Transfer during Evaporation of Cesium from Graphite Surface in an Argon Environment. / Bespala, Evgeny; Novoselov, Ivan; Ushakov, Ivan.
In: MATEC Web of Conferences, Vol. 72, 01011, 09.08.2016.Research output: Contribution to journal › Conference article
}
TY - JOUR
T1 - Heat Transfer during Evaporation of Cesium from Graphite Surface in an Argon Environment
AU - Bespala, Evgeny
AU - Novoselov, Ivan
AU - Ushakov, Ivan
PY - 2016/8/9
Y1 - 2016/8/9
N2 - The article focuses on discussion of problem of graphite radioactive waste formation and accumulation. It is shown that irradiated nuclear graphite being inalienable part of uranium-graphite reactor may contain fission and activation products. Much attention is given to the process of formation of radioactive cesium on the graphite element surface. It is described a process of plasma decontamination of irradiated graphite in inert argon atmosphere. Quasi-one mathematical model is offered, it describes heat transfer process in graphite-cesium-argon system. Article shows results of calculation of temperature field inside the unit cell. Authors determined the factors which influence on temperature change.
AB - The article focuses on discussion of problem of graphite radioactive waste formation and accumulation. It is shown that irradiated nuclear graphite being inalienable part of uranium-graphite reactor may contain fission and activation products. Much attention is given to the process of formation of radioactive cesium on the graphite element surface. It is described a process of plasma decontamination of irradiated graphite in inert argon atmosphere. Quasi-one mathematical model is offered, it describes heat transfer process in graphite-cesium-argon system. Article shows results of calculation of temperature field inside the unit cell. Authors determined the factors which influence on temperature change.
UR - http://www.scopus.com/inward/record.url?scp=84984616683&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=84984616683&partnerID=8YFLogxK
U2 - 10.1051/matecconf/20167201011
DO - 10.1051/matecconf/20167201011
M3 - Conference article
VL - 72
JO - MATEC Web of Conferences
JF - MATEC Web of Conferences
SN - 2261-236X
M1 - 01011
ER -