TY - JOUR
T1 - Fuel evolution in hybrid reactor based on thorium subcritical assembly with open trap as fusion neutron source (computer simulations)
AU - Arzhannikov, Andrey V.
AU - Bedenko, Sergey V.
AU - Ivanov, Aleksandr A.
AU - Modestov, Dmitry G.
AU - Prikhodko, Vadim V.
AU - Sinitsky, Stanislav L.
AU - Shamanin, Igor V.
AU - Shmakov, Vladimir M.
PY - 2019
Y1 - 2019
N2 - Results of computer simulation of the fuel evolution in thorium nuclear cycle in a subcritical assembly in case of thorium-plutonium initial composition is presented in the paper. The simulation is conducted for specialized facility in which a long solenoid with hot plasma is situated inside of the subcritical fuel assembly. The plasma column produces additional neutrons due to D-D fusion reaction that are necessary for a fission reactor with this assembly. Total intensity of neutron emission over all plasma volume with the length of 3m is N = 2 × 1016 neutrons per second. We have chosen the percentage of plutonium 5% in thorium-plutonium initial composition and in this case, the effective coefficient of neutron multiplication is 0.95, as shown by our simulation. The fuel evolution was calculated for duration of operation time 3000 days. As a result, we have demonstrated the decrease in the coefficient of neutron multiplication and in the power of the nuclear fission process in the described time. Results of simulations are discussed.
AB - Results of computer simulation of the fuel evolution in thorium nuclear cycle in a subcritical assembly in case of thorium-plutonium initial composition is presented in the paper. The simulation is conducted for specialized facility in which a long solenoid with hot plasma is situated inside of the subcritical fuel assembly. The plasma column produces additional neutrons due to D-D fusion reaction that are necessary for a fission reactor with this assembly. Total intensity of neutron emission over all plasma volume with the length of 3m is N = 2 × 1016 neutrons per second. We have chosen the percentage of plutonium 5% in thorium-plutonium initial composition and in this case, the effective coefficient of neutron multiplication is 0.95, as shown by our simulation. The fuel evolution was calculated for duration of operation time 3000 days. As a result, we have demonstrated the decrease in the coefficient of neutron multiplication and in the power of the nuclear fission process in the described time. Results of simulations are discussed.
KW - Neutron from deuterium plasma
KW - Nuclear fuel evolution
KW - Thorium hybrid reactor
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U2 - 10.1585/PFR.14.2402101
DO - 10.1585/PFR.14.2402101
M3 - Article
AN - SCOPUS:85069969201
VL - 14
JO - Plasma and Fusion Research
JF - Plasma and Fusion Research
SN - 1880-6821
M1 - 2402101
ER -