Fuel elements of nuclear reactors

Samoilov, A. G.; Volkov, V. S.

doi:10.1007/bf01481447

Cited by 9 publications

(7 citation statements)

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“…The following composition of aluminum alloy 6082 (AD35) was used in the research as the cladding material (in wt.%): Al + 0.8% Mg + 1.1% Si + 0.5% Mn + + 0.27% Fe + 0.12% Cr + 0.09% Zn + + 0.1% Cu. Its chemical composition and characteristics are close to the alloys SAV-1 and 6061, that are used for production of fuel claddings for research reactors [3,4]. UO 2 -Al was used as the pellet composition, and HfO 2 -Al was used as the simulating composition.…”

Section: Samples Fuel Rod Dummies Research Methodsmentioning

confidence: 99%

“…Nb (ρU = 15.8 g/cm 3 ), U + 9% wt. Mo (ρU = 15.5 g/cm 3 ) and uranium compounds: U 3 Si (ρU = 15.0 g/cm 3 ), U 3 Si 2 (ρU = 11.3 g/cm 3 ), UO 2 (ρU = 9.2 g/cm 3 ) [4,5]. At the initial stage, compositions UAl x -Al, UO 2 -Al, U 3 O 8 -Al were used, which became widespread.…”

mentioning

confidence: 99%

“…Moreover, in most cases they provide metallurgical bonding between the cladding and the core. This allows to significantly reduce operating temperatures of fuel compositions, increase their service life and structural rigidity [4]. Various EEJP.…”

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confidence: 99%

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Research and Development of Fuel Rods Metallurgically Bonded with Fuel Cladding for Nuclear Installations

Belash

Kushtym

Zigunov

et al. 2021

EEJP

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The design and scheme for manufacturing fuel rods metallurgically bonded with ribbed aluminum claddings using hot isostatic pressing and contact-reactive brazing are presented. It is shown that the developed scheme can be used both for production of dispersive fuels and high-density fuels based on uranium alloys. The results of investigations of brazed joints of aluminum cladding with a matrix composition based on aluminum and with samples of E110 alloy through copper and silumin coatings are presented. The results of research of brazed joints of an aluminum cladding with an aluminum-based matrix composition and samples of zirconium alloy E110 made through copper and silumin coating are presented. The strength of brazed joints, composition of diffusion layers formed as a result of contact-reactive brazing in a high vacuum have been determined. The modes of hot isostatic pressing that provide crimping of the ribbed cladding of fuel pellets and rods and obtaining a metallurgical bonding between their surfaces have been defined. It is shown that satisfactory bond strength is provided starting from the temperature of 610 °С. The maximum strength values obtained on the compounds Al-(Al+12% Si)-Zr and Al-Cu-Zr are 57.0 MPa and 55.3 MPa respectively. The fracture of the of aluminum samples joints, obtained with the Cu layer at a temperature of 620 °C, occurs on threaded joints at the strength value of 82 MPa. The results of research of the composition of diffusion layers formed by brazing compounds Al-(Al + 12% Si)-Zr and Al-Cu-Zr are presented. It was established that hot pressing provides the best results for manufacturing of fuel rod dummies in the studied range of modes at a temperature of 630 °C, a pressure of 380 MPa and exposure of 20 minutes.

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Section: Samples Fuel Rod Dummies Research Methodsmentioning

confidence: 99%

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confidence: 99%

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Research and Development of Fuel Rods Metallurgically Bonded with Fuel Cladding for Nuclear Installations

Belash

Kushtym

Zigunov

et al. 2021

EEJP

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“…For nuclear power engineering, it is promising to use dispersive NF, in which there are no direct contacts between particles of fissile material due to their uniform distribution in a matrix with high thermal conductivity and low neutron absorption. This provides high thermal conductivity and mechanical properties, radiation resistance and strength of the fuel compositions, higher burnup of fissile material and localization of fission products [1][2][3][4][5].…”

Section: Introductionmentioning

confidence: 99%

Plasmachemical synthesis and the assessment of the thermal conductivity of fuel compounds “UO2–MgO”

Shamanin

Karengin

Novoselov

et al. 2019

AIP Conference Proceedings

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The process of plasma-chemical synthesis from water-organic nitrate solutions of uranium and magnesium of fuel compositions including a matrix of magnesium oxide with a high thermal conductivity and low neutron absorption is investigated. The compositions of the solutions, including acetone (ethanol), as well as the regimes that providing the direct synthesis of "UO2-MgO" fuel compositions of different concentrations in air plasma are determined. The calculation of their thermal conductivity and comparison with experimental data are presented.

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“…One of the promising areas for further development of nuclear energy is the creation of fuel compositions (FC), including fissionable metal oxides (uranium, plutonium, and thorium) and a matrix of metal oxides (beryllium, magnesium, etc.) with high thermal conductivity and low cross section for resonant neutron absorption [1][2][3][4][5].…”

Section: Introductionmentioning

confidence: 99%

Model of reactor for plasma treatment of dispersed water-organic nitrate solutions of metals

Karengin¹,

Novoselov²,

Golovkov³

2019

AIP Conference Proceedings

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The paper proposes a mathematical model of the reactor, which describes the process of treatment of dispersed water-organic nitrate solutions of metals at air-plasma flow temperatures more than 1500 K. Regularities and a quantitative comparison were made to show the effect of the initial values of the air-plasma flow parameters (temperature, velocity) and the WONS droplet parameters (size, velocity) on the rate of their evaporation in the reactor. Process conditions were established that ensure a high evaporation rate of dispersed solutions in the airplasma flow. CALCULATION OF BURNING INDEXES AND COMPOSITIONS OF WONS Lower heat value and adiabatic combustion temperature of WONS including organic component (ethanol, acetone) and mixed water-nitric solutions of fissile materials (uranium, plutonium, and thorium) and matrix materials (beryllium and magnesium) are determined from formulas (1) and (2) [13]:

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Fuel elements of nuclear reactors

Cited by 9 publications

References 0 publications

Research and Development of Fuel Rods Metallurgically Bonded with Fuel Cladding for Nuclear Installations

Research and Development of Fuel Rods Metallurgically Bonded with Fuel Cladding for Nuclear Installations

Plasmachemical synthesis and the assessment of the thermal conductivity of fuel compounds “UO2–MgO”

Model of reactor for plasma treatment of dispersed water-organic nitrate solutions of metals

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