Evaluation of neutron activation of intermetallic matrices for dispersive nuclear fuel obtained by SH-synthesis; Journal of Physics: Conference Series; Vol. 1439 : Modern Problems of Physics and Technology

Manylion Llyfryddiaeth
Parent link:Journal of Physics: Conference Series
Vol. 1439 : Modern Problems of Physics and Technology.— 2020.— [012040, 6 p.]
Awduron Eraill: Balachkov M. M. Maxim Mikhailovich, Dolmatov O. Yu. Oleg Yurevich, Kuznetsov M. S. Mikhail Sergeyevich, Kostyuchenko K. S. Kristina Sergeevna, Pimenov N. O. Nikita Olegovich, Permikin A. A. Anton Andreevich
Crynodeb:Title screen
The paper describes a technique for obtaining intermetallic matrix materials based on Zr-Al and Ni-Al systems for dispersive nuclear fuel. This type of fuel is planned to be used in existing and future high-temperature nuclear reactors. Physical and mathematical modelling of the process of activation of matrices by neutron radiation showed that upon reaching the value of thermal neutron fluence of the order of 2.76·1021 n·cm-2 , the activity of Zr-Al and Ni-Al matrices was 1.3·1010 and 0.2·1010 Bq/g, respectively. The analysis showed that in terms of exposure of irradiated fuel it is preferable to use a matrix based on the zirconium-aluminium system.
Iaith:Saesneg
Cyhoeddwyd: 2020
Pynciau:
Mynediad Ar-lein:http://earchive.tpu.ru/handle/11683/64884
http://dx.doi.org/10.1088/1742-6596/1347/1/012040
Fformat: Electronig Pennod Llyfr
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=663824

MARC

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200 1 |a Evaluation of neutron activation of intermetallic matrices for dispersive nuclear fuel obtained by SH-synthesis  |f M. M. Balachkov, O. Yu. Dolmatov, M. S. Kuznetsov [et al.] 
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330 |a The paper describes a technique for obtaining intermetallic matrix materials based on Zr-Al and Ni-Al systems for dispersive nuclear fuel. This type of fuel is planned to be used in existing and future high-temperature nuclear reactors. Physical and mathematical modelling of the process of activation of matrices by neutron radiation showed that upon reaching the value of thermal neutron fluence of the order of 2.76·1021 n·cm-2 , the activity of Zr-Al and Ni-Al matrices was 1.3·1010 and 0.2·1010 Bq/g, respectively. The analysis showed that in terms of exposure of irradiated fuel it is preferable to use a matrix based on the zirconium-aluminium system. 
461 |t Journal of Physics: Conference Series 
463 |t Vol. 1439 : Modern Problems of Physics and Technology  |o VIII International Youth Scientific School-Conference (MPPT2019) 15–20 April 2019, Moscow, Russian Federation  |v [012040, 6 p.]  |d 2020 
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701 1 |a Balachkov  |b M. M.  |c Specialist in the field of nuclear technologies  |c Technician of Tomsk Polytechnic University  |f 1995-  |g Maxim Mikhailovich  |3 (RuTPU)RU\TPU\pers\46466  |9 22131 
701 1 |a Dolmatov  |b O. Yu.  |c Physicist  |c Candidate of physical and mathematical sciences  |f 1967-  |g Oleg Yurevich  |3 (RuTPU)RU\TPU\pers\32619  |9 16531 
701 1 |a Kuznetsov  |b M. S.  |c physicist  |c Associate Professor of Tomsk Polytechnic University, Candidate of Technical Sciences  |f 1984-  |g Mikhail Sergeyevich  |3 (RuTPU)RU\TPU\pers\31208  |9 15404 
701 1 |a Kostyuchenko  |b K. S.  |g Kristina Sergeevna 
701 1 |a Pimenov  |b N. O.  |g Nikita Olegovich 
701 1 |a Permikin  |b A. A.  |c Specialist in the field of nuclear technologies  |c Engineer of Tomsk Polytechnic University  |f 1995-  |g Anton Andreevich  |3 (RuTPU)RU\TPU\pers\46465  |9 22130 
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