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

I. V. Shamanin, S. V. Bedenko, V. M. Shmakov, D. G. Modestov, V. V. Knyshev, I. O. Lutsik, S. D. Polozkov

Research output: Contribution to journalArticlepeer-review


Spatial kinetics peculiarities of an innovative hybrid nuclear power facility with an extended neutron source based on a magnetic trap are investigated. The investigated fusion-fission facility includes a reactor plant the core of which consists of a unitized HTGR reactor thorium-plutonium fuel block assembly and a lengthy magnetic trap which runs through the near-axis reactor core region. The engineering solution for the neutron plasma generator is based on an online 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 a pulse periodic mode in the investigated hybrid facility configuration, and, at a certain pulse ratio, one should expect the formation of a fission wave that diverges from the axial part of the system and propagates over the volume of 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's blanket. The paper presents the results of a study into the steady-state and spatial-time performance of neutron fluxes and the power density dynamics in the facility under investigation. The steady-state neutronic performance and the spatial-time fission wave propagation were simulated using the PRIZMA code developed at VNIITF.

Original languageEnglish
Pages (from-to)17-26
Number of pages10
JournalIzvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika
Issue number2
Publication statusPublished - Jul 2020


  • D-D neutron plasma pulse periodic generator
  • Fission wave
  • Fusion- fission hybrid reactor

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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