Initiation and propagation of nuclear burning wave in fast reactor
- 1. National Science Center, Kharkov Institute of Physics and Technology, Kharkov (Ukraine)
Description
The regime of the nuclear burning wave (NBW) in a fast reactor (FR) is described using the non-stationary diffusion equation for neutron transport and equation of the fuel component burn-up and of nuclear kinetics for precursor nuclei of delayed neutrons. A critical two-zone fast reactor of cylindrical form with metal fuel of the U-Pu cycle is considered. The initiation of nuclear burning in an enriched ignition zone by means of an external neutron flux that is turned off at an early stage of FR operation has been simulated. The possibility of creating a self-organizing regime of a running NBW in the breeding zone along the reactor axis has been demonstrated. The neutron leakage in a transverse direction was taken into account using the concept of radial buckling. The calculation results of the space-time evolution of neutron flux in this system using the effective multi-group approximation are presented. The average fuel burn-up is about 50%. The velocity of NBW propagation strongly depends on the transverse size of FR. For example, in the reactor of 110 cm radius and 500 cm length the NBW velocity is about 22 cm/year. (author)
Additional details
Publishing Information
- Publisher
- Tokyo Inst. of Technology
- Imprint Place
- Tokyo (Japan)
- ISBN
- 978-4-903054-15-5
- Imprint Title
- Innovative nuclear energy systems for sustainable development of the world
- Imprint Pagination
- 727 p.
- Journal Page Range
- p. 163-169
Conference
- Title
- 2. COE-INES international symposium
- Acronym
- INES-2
- Dates
- 26-30 Nov 2006
- Place
- Yokohama, Kanagawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 40008915
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING; BUCKLING; BURNUP; DELAYED NEUTRON PRECURSORS; FAST REACTORS; FEEDBACK; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; NEUTRON LEAKAGE; NEUTRON TRANSPORT; REACTIVITY; REACTOR KINETICS
- Descriptors DEC
- DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; EPITHERMAL REACTORS; EQUATIONS; ISOTOPES; KINETICS; NEUTRAL-PARTICLE TRANSPORT; NEUTRON TRANSPORT THEORY; NUCLEAR FUEL CONVERSION; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION TRANSPORT; RADIOISOTOPES; REACTORS; TRANSPORT THEORY
Optional Information
- Notes
- 14 refs., 6 figs., 1 tab. Imprint:Also published as Progress in Nuclear Energy (Mar 2008). V.50(2-6)