Abstract
Tomsk Polytechnic University is conducting a series of experiments to develop a nuclear fuel manufacturing technology required for a new-generation innovative nuclear systems. In this study, the thermal conductivity and thermophysical properties were calculated for the proposed nuclear fuel, which are necessary before proceeding to the construction stage. The cylindrical fuel compact consisting of spherical coated constituents (Pu,Th)O 2 of BISO type, were sintered together within a graphite matrix (C). Also, a composite material made of nuclear fuel (Pu,Th)O 2 and refractory oxides BeO/MgO, were prepared using plasma-chemical synthesis method. The development of a fuel pellet with desired physical properties that can be exposed for a long time under irradiation in a high-temperature gas-cooled thorium reactor core is the main technological advantage of the present study.
| Original language | English |
|---|---|
| Title of host publication | V International Conference for Young Scientists, Post-Graduate Students and Students �Isotopes |
| Subtitle of host publication | Technologies, Materials and Application�, ITMA 2018 |
| Editors | Gagik Ashot Martoyan, Anna Godymchuk, Liudmyla Rieznichenko |
| Publisher | American Institute of Physics Inc. |
| ISBN (Electronic) | 9780735418318 |
| DOIs | |
| Publication status | Published - 18 Apr 2019 |
| Event | 5th International Conference for Young Scientists, Post-Graduate Students and Students on Isotopes: Technologies, Materials and Application, ITMA 2018 - Tomsk, Russian Federation Duration: 19 Nov 2018 → 23 Nov 2018 |
Publication series
| Name | AIP Conference Proceedings |
|---|---|
| Volume | 2101 |
| ISSN (Print) | 0094-243X |
| ISSN (Electronic) | 1551-7616 |
Conference
| Conference | 5th International Conference for Young Scientists, Post-Graduate Students and Students on Isotopes: Technologies, Materials and Application, ITMA 2018 |
|---|---|
| Country | Russian Federation |
| City | Tomsk |
| Period | 19.11.18 → 23.11.18 |
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ASJC Scopus subject areas
- Physics and Astronomy(all)
Cite this
Thermo-physical properties of dispersion nuclear fuel for a new-generation reactors : A computational approach. / Bedenko, Sergey; Karengin, Alexander; Ghal-Eh, Nima; Alekseev, Nikita; Knyshev, Vladimir; Shamanin, Igor.
V International Conference for Young Scientists, Post-Graduate Students and Students �Isotopes: Technologies, Materials and Application�, ITMA 2018. ed. / Gagik Ashot Martoyan; Anna Godymchuk; Liudmyla Rieznichenko. American Institute of Physics Inc., 2019. 020002 (AIP Conference Proceedings; Vol. 2101).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution
}
TY - GEN
T1 - Thermo-physical properties of dispersion nuclear fuel for a new-generation reactors
T2 - A computational approach
AU - Bedenko, Sergey
AU - Karengin, Alexander
AU - Ghal-Eh, Nima
AU - Alekseev, Nikita
AU - Knyshev, Vladimir
AU - Shamanin, Igor
PY - 2019/4/18
Y1 - 2019/4/18
N2 - Tomsk Polytechnic University is conducting a series of experiments to develop a nuclear fuel manufacturing technology required for a new-generation innovative nuclear systems. In this study, the thermal conductivity and thermophysical properties were calculated for the proposed nuclear fuel, which are necessary before proceeding to the construction stage. The cylindrical fuel compact consisting of spherical coated constituents (Pu,Th)O 2 of BISO type, were sintered together within a graphite matrix (C). Also, a composite material made of nuclear fuel (Pu,Th)O 2 and refractory oxides BeO/MgO, were prepared using plasma-chemical synthesis method. The development of a fuel pellet with desired physical properties that can be exposed for a long time under irradiation in a high-temperature gas-cooled thorium reactor core is the main technological advantage of the present study.
AB - Tomsk Polytechnic University is conducting a series of experiments to develop a nuclear fuel manufacturing technology required for a new-generation innovative nuclear systems. In this study, the thermal conductivity and thermophysical properties were calculated for the proposed nuclear fuel, which are necessary before proceeding to the construction stage. The cylindrical fuel compact consisting of spherical coated constituents (Pu,Th)O 2 of BISO type, were sintered together within a graphite matrix (C). Also, a composite material made of nuclear fuel (Pu,Th)O 2 and refractory oxides BeO/MgO, were prepared using plasma-chemical synthesis method. The development of a fuel pellet with desired physical properties that can be exposed for a long time under irradiation in a high-temperature gas-cooled thorium reactor core is the main technological advantage of the present study.
UR - http://www.scopus.com/inward/record.url?scp=85064856143&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85064856143&partnerID=8YFLogxK
U2 - 10.1063/1.5099594
DO - 10.1063/1.5099594
M3 - Conference contribution
AN - SCOPUS:85064856143
T3 - AIP Conference Proceedings
BT - V International Conference for Young Scientists, Post-Graduate Students and Students �Isotopes
A2 - Martoyan, Gagik Ashot
A2 - Godymchuk, Anna
A2 - Rieznichenko, Liudmyla
PB - American Institute of Physics Inc.
ER -