TY - JOUR
T1 - Neutron data field in a fission reactor core with fusion neutron source at pulse-periodic operation
AU - Shamanin, I. V.
AU - Shmakov, V. M.
AU - Modestov, D. G.
AU - Bedenko, S. V.
AU - Polozkov, S. D.
AU - Prikhodko, V. V.
AU - Arzhannikov, A. V.
N1 - Funding Information:
This work was supported by the Russian Foundation for Basic Research (project no. 19-29-02005 mk).
Publisher Copyright:
© Published under licence by IOP Publishing Ltd.
Copyright:
Copyright 2020 Elsevier B.V., All rights reserved.
PY - 2020/10/12
Y1 - 2020/10/12
N2 - Results are presented on the distinctive features of the energy release dynamics in the hybrid thorium reactor operating in combination with the neutron source based on the extended magnetic mirror trap. In the reactor core configuration under study, the high-Temperature plasma column is formed in a pulse-periodic mode. At a certain duty cycle (pulse ratio) of the plasma column formation, it can be expected that the fission "wave"will be formed diverging from the axial region of the system and propagating in the radial direction in the fuel assembly (blanket). Under such conditions, in order to correct the resulting offset of the energy release distribution, it is necessary to optimize the fuel composition of the assembly in order to obtain the most appropriate radial distributions of physical parameters. The studies are carried out on the basis of the full-scale model of the reactor core, in which the axial region is modified: The extended magnetic mirror trap operating as a source of fusion neutrons is installed in the reactor core axial region.
AB - Results are presented on the distinctive features of the energy release dynamics in the hybrid thorium reactor operating in combination with the neutron source based on the extended magnetic mirror trap. In the reactor core configuration under study, the high-Temperature plasma column is formed in a pulse-periodic mode. At a certain duty cycle (pulse ratio) of the plasma column formation, it can be expected that the fission "wave"will be formed diverging from the axial region of the system and propagating in the radial direction in the fuel assembly (blanket). Under such conditions, in order to correct the resulting offset of the energy release distribution, it is necessary to optimize the fuel composition of the assembly in order to obtain the most appropriate radial distributions of physical parameters. The studies are carried out on the basis of the full-scale model of the reactor core, in which the axial region is modified: The extended magnetic mirror trap operating as a source of fusion neutrons is installed in the reactor core axial region.
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U2 - 10.1088/1742-6596/1647/1/012007
DO - 10.1088/1742-6596/1647/1/012007
M3 - Conference article
AN - SCOPUS:85096360793
VL - 1647
JO - Journal of Physics: Conference Series
JF - Journal of Physics: Conference Series
SN - 1742-6588
IS - 1
M1 - 012007
T2 - 47th Zvenigorod International Conference on Plasma Physics and Controlled Fusion, ICPAF 2020
Y2 - 16 March 2020 through 20 March 2020
ER -