PRIZMA status

Kandiev, Ya. Z.; Kashaeva, E. A.; Khatuntsev, K.E.; Kuropatenko, E.S.; Lobanova, L. V.; Lukin, G.N.; Malakhov, Anton; Malyshkin, G.N.; Modestov, D.G.; Mukhamadiev, R.F.; Orlov, V. G.; Samarin, S.I.; Serova, E. V.; Spirina, S.G.; Vakhonina, T.V.; Voronina, N.A.; Zatsepin, O.V.

doi:10.1016/j.anucene.2014.09.006

Cited by 19 publications

(4 citation statements)

References 8 publications

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“…As to loses of the neutron flux through the right and left ends of the assembly, they are 9% and 4%, respectively. The effective neutron multiplication coefficient, the neutron reproduction coefficient, the distribution of neutron fluxes and energy release are obtained in the frame of using the Monte Carlo code of PRISMA [4,5] with continuous neutron data (ENDF/B-VII.1). Calculations of the nuclear fuel kinetics are carried out using the RISC code [6] with data on the decays from ENDF/B-VII.O and with usage of the calculation results of the fuel burnup.…”

Section: Computer Codes and Results Of Simulationmentioning

confidence: 99%

Fuel Evolution in Hybrid Reactor Based on Thorium Subcritical Assembly with Open Trap as Fusion Neutron Source (Computer Simulations)

Аржанников

Bedenko

Ivanov

et al. 2019

Plasma and Fusion Research

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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 3 m is N = 2 × 10 16 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.

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Section: Computer Codes and Results Of Simulationmentioning

confidence: 99%

Fuel Evolution in Hybrid Reactor Based on Thorium Subcritical Assembly with Open Trap as Fusion Neutron Source (Computer Simulations)

Аржанников

Bedenko

Ivanov

et al. 2019

Plasma and Fusion Research

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“…It should be noted that in the "PNS -blanket" configuration under study, the plasma column is formed in a repetitively pulsed mode, and the "wave" of fission of ( wg Pu-Th)O 2 -fuel nuclei propagates from the axial region over the entire multiplicating part in proportion to the time with the PNS operation. The study of the dynamics of fission of fuel nuclei was carried out using the PRIZMA code (Kandiev et al 2015) in combination with subprograms specially developed by the employees of the All-Russian Scientific Research Institute of Technical Physics (RFNC-VNIITF).…”

Section: Methodsmentioning

confidence: 99%

Fusion-fission hybrid reactor facility: power profiling

Bedenko¹,

Lutsik²,

Matyushin³

et al. 2023

NUCET

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The current state of research in the field of nuclear and thermonuclear power aimed at creating power generation plants makes it possible to predict the further development of modern power industry in the direction hybrid reactor power plants. Such hybrid systems include a tokamak with reactor technologies, worked out in detail in Russia, and systems with an additional source of neutrons. Power generation plants using tokamaks and accelerators with the required level of proton energy will be of exceptionally large size and power, which will postpone their construction on an industrial scale to the distant future. The ongoing research is aimed at the development of small generation and has the prospect of entering the field of energy use in a shorter period. The hybrid reactor facility under study consists of an axisymmetric assembly of fuel blocks of a high-temperature gas-cooled reactor and a linear plasma source of additional neutrons. The paper demonstrates the results of optimization plasma-physical, thermophysical and gas-dynamic studies, the purpose of which is to level the distortions of the power density field, which are formed in the volume of the multiplicating part of the facility due to the pulsed operation of the plasma source of D-T-neutrons. The studies on increasing the “brightness” of the source and modeling its operating modes were carried out using the DOL and PRIZMA programs. The thermophysical optimization and gas-dynamic calculations were performed using the verified SERPENT and FloEFD software codes. The calculations were made on a high-performance cluster of the Tomsk Polytechnic University.

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“…The steady-state neutronic performance and the spacetime fission wave propagation were simulated using the PRIZMA software package (Kandiev et al 2015), with the ENDF/B-VII.1 library of evaluated incident-neutron data (Nuclear Energy Agency acces. 2020), developed at FSUE RFNC-VNIITF.…”

Section: Computational Research Methodsmentioning

confidence: 99%

Power density dynamics in a nuclear reactor with an extended in-core pulse-periodic neutron source based on a magnetic trap

Shamanin¹,

Bedenko²,

Shmakov³

et al. 2020

NUCET

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The article examines the features of the spatial kinetics of an innovative hybrid nuclear power facility with an extended neutron source based on a magnetic trap. The fusion-fission facility under study includes a reactor plant, the core of which consists of an assembly of thorium-plutonium fuel blocks of the HGTRU reactor of a unified design and a long magnetic trap that penetrates the near-axial region of the core. The engineering solution for the neutron plasma generator is based on an operating gas-dynamic trap based on a fusion neutron source (GDT-FNS) developed at the Novosibirsk G.I. Budker Nuclear Physics Institute of the Siberian Branch of the Russian Academy of Sciences. The GDT-FNS high-temperature plasma pinch is formed in pulse-periodic mode in the investigated hybrid facility configuration, and, at a certain pulse rate, one should expect the formation of a fission wave that diverges from the axial part of the system and propagates throughout the fuel block assembly in a time correlation with the fast D-D neutron pulse source. In these conditions, it is essential to study the fission wave propagation process and, accordingly, the power density distribution formation within the facility blanket. The paper presents the results of a study on the steady-state and space-time performances of neutron fluxes and the power density dynamics in the facility under investigation. The steady-state neutronic performance and the space-time fission wave propagation were simulated using the PRIZMA software package developed at FSUE RFNC-VNIITF.

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PRIZMA status

Cited by 19 publications

References 8 publications

Fuel Evolution in Hybrid Reactor Based on Thorium Subcritical Assembly with Open Trap as Fusion Neutron Source (Computer Simulations)

Fuel Evolution in Hybrid Reactor Based on Thorium Subcritical Assembly with Open Trap as Fusion Neutron Source (Computer Simulations)

Fusion-fission hybrid reactor facility: power profiling

Power density dynamics in a nuclear reactor with an extended in-core pulse-periodic neutron source based on a magnetic trap

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PRIZMA status

Cited by 19 publications

References 8 publications

Fuel Evolution in Hybrid Reactor Based on Thorium Subcritical Assembly with Open Trap as Fusion Neutron Source (Computer Simulations)

Fuel Evolution in Hybrid Reactor Based on Thorium Subcritical Assembly with Open Trap as Fusion Neutron Source (Computer Simulations)

﻿Fusion-fission hybrid reactor facility: power profiling

Power density dynamics in a nuclear reactor with an extended in-core pulse-periodic neutron source based on a magnetic trap

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Fusion-fission hybrid reactor facility: power profiling