Solution of neutron transport multigroup equations system in subcritical systems

Shamanin, I. V.; Bedenko, Sergey V.; Нестеров, В. Н.; Lutsik, Igor O.; Prets, Anatoly Andreevich

doi:10.26583/npe.2017.4.04

Cited by 4 publications

(3 citation statements)

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“…Its active part's region adjoining the axis is substituted by a cylindrical vacuum chamber containing high-temperature plasma that generates extra neutrons as a result of D-D and D-T thermonuclear reactions. This plasma part has a chamber mated to it for injecting beams of high-energy neutral deuterium and tritium atoms (Anikeev et al 2015, Yurov et al 2016). The magnetic field in these two portions of the vacuum chamber, which contain high-temperature plasma, thermally isolates the plasma from the chamber walls in the radial direction (Arzhannikov et al 2019).…”

Section: Methodsmentioning

confidence: 99%

“…Passive reactivity should be achieved with the use of SRs and BAs in conjunction with a plasma neutron generator which, together with the SR and BA system, is required to compensate for the effects caused by the nuclear fuel burn-up, and by the blanket slagging and poisoning in the process of the startup and during long-term operation. This was achieved in a 69-group diffusion approximation by the joint use of the WIMS-D5B (ENDF/B-VII.0) code (Pazirandeh et al 2011) and an iterative method used to solve the neutron transport equation (Shamanin et al 2017). The calculations take into account the effects leading to a change in the thermophysical properties of the blanket and in the temperature of the compact's fuel part.…”

Section: Calculation Of Shim Elementsmentioning

confidence: 99%

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Subcriticality control elements in a reactor system with an extended plasma source of neutrons with regard for temperature

Knyshev¹,

Karengin²,

Shamanin³

2021

NUCET

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Materials have been selected for the shim rods and burnable absorbers to compensate for the excessive reactivity of the facility’s blanket part and to provide for the possibility of reactivity control in conjunction with a plasma source of neutrons. Burnable absorber is a layer of zirconium diboride (ZrB2) with a thickness of 100 μm applied to the surface of fuel compacts. Boron carbide (B4C) rods installed in the helium flow channels and used to bring the entire system into a state with keff = 0.95 have been selected as the shim rod material. Throughout its operating cycle, the facility is subcritical and is controlled using the neutron flux from the plasma source. Verified codes, WIMS-D5B (ENDF/B-VII.0) and MCU5TPU (MCUDВ50), as well as a modern system of constants were used for the calculations. The facility’s neutronic performance was simulated with regard for the changes in the inner structure and temperature of the microencapsulated fuel and fuel compact materials caused by long-term irradiation and by the migration of fission fragments and gaseous chemical compounds.

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Section: Methodsmentioning

confidence: 99%

Section: Calculation Of Shim Elementsmentioning

confidence: 99%

Subcriticality control elements in a reactor system with an extended plasma source of neutrons with regard for temperature

Knyshev¹,

Karengin²,

Shamanin³

2021

NUCET

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“…All group values and, consequently, the values averaged over the spectrum to be entered in the expression for determination of effective neutron multiplication factor k eff were determined based on the partial neutron flux values obtained (Golovatsky et al 2010a;Shamanin et al 2017). Thus, the value of k eff at the beginning of fuel irradiation amounted to 1.144 taking into account the burnable neutron absorber.…”

Section: Variation Of Fluxes Damaging and Thermal Neutrons During Fuementioning

confidence: 99%

Extension of lifespan of graphite in fuel blocks of high-temperature gas-cooled reactors as the resource for ensuring design values of nuclear fuel burn-up

Bulakh¹,

Kostylev²,

Нестеров³

et al. 2019

NUCET

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High-temperature gas-cooled reactor (HTGR) is one of promising candidates for new generation of nuclear power reactors. This type of nuclear reactor is characterized with the following principal features: highly efficient generation of electricity (thermal efficiency of about 50%); the use of high-temperature heat in different production processes; reactor core self-protection properties; practical exclusion of reactor core meltdown in case of accidents; the possibility of implementation of various nuclear fuel cycle options; reduced radiation and thermal effects on the environment, forecasted acceptability of financial performance with respect to cost of electricity as compared with alternative energy sources. The range of output coolant temperatures in high-temperature reactors within the limits of 750–950 °C predetermines the use of graphite as the structural material of the reactor core and helium as the inert coolant. Application of graphite ensures higher heat capacity of the reactor core and its practical non-meltability. Residence time of reactor graphite depends on the critical value of fluence of damaging neutrons (neutrons with energies above 180 keV). In its turn, the value of critical neutron fluence is determined by the irradiation temperature and flux density of accompanying gamma-radiation. The values of critical fluence for graphite decrease within high-temperature region of 800–1000 °C to 1·1022 – 2·1021 cm–2, respectively. The compactness of the core results in the increase of the fracture of damaging neutrons in the total flux. These circumstances predetermine relatively low values of lifespan of graphite structures in high-temperature reactors. Design features and operational parameters of GT-MHR high-temperature gas-cooled reactor are described in the present paper. Results of neutronics calculations allowing determining the values of damaging neutron flux, nuclear fuel burnup and expired lifespan of graphite of fuel blocks were obtained. The mismatch between positions of the maxima in the dependences of fuel burnup and exhausted lifespan of graphite in fuel blocks along the core height is demonstrated. The map and methodology for re-shuffling fuel blocks of the GT-MHR reactor core were developed as the result of analysis of the calculated data for ensuring the matching between the design value of the fuel burnup and expected total graphite lifespan.

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A fuel for generation IV nuclear energy system: Isotopic composition and radiation characteristics

Bedenko

Ghal-Eh

Lutsik

et al. 2019

Applied Radiation and Isotopes

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Solution of neutron transport multigroup equations system in subcritical systems

Abstract: The iteration process of the neutron transport equation solution in diffuse 28 group approximation was implemented. A PuO 2 fueled thermoelectric generator providing thermal and electric power for space vehicles was researched as a system.

Cited by 4 publications

References 0 publications

Subcriticality control elements in a reactor system with an extended plasma source of neutrons with regard for temperature

Subcriticality control elements in a reactor system with an extended plasma source of neutrons with regard for temperature

Extension of lifespan of graphite in fuel blocks of high-temperature gas-cooled reactors as the resource for ensuring design values of nuclear fuel burn-up

A fuel for generation IV nuclear energy system: Isotopic composition and radiation characteristics

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