Protective structures for storing spent nuclear fuel from the Zaporozhye NPP

Zalubovsky, I. I.; Pismenetskiy, S. A.; Рудычев, В.Г.; Klimov, S. P.; Kravets, V. M.; Luchnaja, A. E.; A.Tishchenko, V.; Рудычев, Е.В.

doi:10.1007/s10512-012-9555-0

Cited by 4 publications

(3 citation statements)

References 1 publication

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“…Different shields with different densities and thicknesses made from dispersed Pb, depleted uranium U, depleted uranium dioxide UO 2 , as well as the shields with initial density of the Fe and U are considered. The long-lived isotopes: 134 Cs, 137 Cs, and 154 Eu are chosen as sources of SNF gamma-rays [7]. In Fig.…”

Section: Numerical Resultsmentioning

confidence: 99%

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The Efficiency of Radiation Shielding Made From Materials With High Atomic Number and Low Mass Density

Рудычев¹,

Azarenkov²,

Гірка³

et al. 2021

Problems of Atomic Science and Technology

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The radiation shielding from γ-quanta of the existing transport containers (TC) for transportation of spent nuclear fuel (SNF) is made of steel or steel plus Pb 25…30 cm thick and weighting ~ 60…80 t. The application of materials with high atomic number, dispersed (solids grinded to a powdery state) to the densities in the range 4 < ρ < 8 g/cm3, is investigated. Simulations based on the Monte Carlo method show that at the densities of dispersed depleted U larger than 5 g/cm3 and shielding thicknesses of more than 30 cm, the absorption of γ-quanta of SNF is greater than that of the shielding made of steel of the same thickness. The application of such materials, while the weight characteristics of the shields are not exceeded, provides radiation shielding for SNF with the high burnup rate and the smaller cooling time or larger amount of the transported SNF.

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Section: Numerical Resultsmentioning

confidence: 99%

“…The spectral composition of the SNF gammaradiation changes with the SNF cooling time due to different half-lives of long-lived isotopes. Isotopes 134 Cs, 137 Cs, and 154 Eu were shown in [7] to make the main contribution to the spectral composition. Fig.…”

Section: Fig 3 Spectral Gamma Distributions Produced By Snfmentioning

confidence: 98%

The Efficiency of Radiation Shielding Made From Materials With High Atomic Number and Low Mass Density

Рудычев¹,

Azarenkov²,

Гірка³

et al. 2021

Problems of Atomic Science and Technology

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“…The elemental composition of the fuel emission zone, which is planned to be transported in the TCs to the storage by the dry method, was modeled by homogeneous SNF with a density of 3.5 g/cm 3 containing 238 U 52.3%, 40 Zr 25.8%, 26 Fe 14.6%, 16 O 7.3% [8]. It is shown in [7] that the flux of -quanta on the surface of the source is determined by the near-surface layer of SNF. As the initial characteristics of -quanta, the energy and angular distributions of -radiation from a layer of homogenized SNF ≈ 10 cm thick were used.…”

Section: Calculation Methodsmentioning

confidence: 99%

EFFICIENCY OF COMBINED Fe AND Pb RADIATION SHIELD OF TRANSPORT CASKS FOR SNF TRANSPORTATION

Рудычев¹,

Azarenkov²,

Гірка³

et al. 2022

Problems of Atomic Science and Technology

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The possibility of increasing the efficiency of combined iron and lead shielding of transport containers (TC) for SNF transportation by railroad is studied. Models for the transport of SNF γ-quanta are developed, that make it possible to determine the dose rates behind thick shields using the Monte Carlo method. It is shown that for layers of the same mass thickness: the layer of Fe with the thickness of 15 cm, and the layer of Pb with the thickness of 10.4 cm which is equivalent to 15 cm of iron, placement of Fe in the first layer, and Pb in the second layer provides increase of attenuation of the gamma flux by more than 2 times as compared with the reverse order. The attenuation of SNF neutrons by Fe and Pb shields is studied. The gamma flux from SNF can be decreased by ∼ 1.5 times by placement of the most of Fe to the first layer without changing the weight of both layers, in the HI-STAR190UA TC.

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Change in radiation characteristics outside the SNF storage container as an indicator of fuel rod cladding destruction

Рудычев

Azarenkov

Гірка

et al. 2021

Nuclear Engineering and Technology

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Protective structures for storing spent nuclear fuel from the Zaporozhye NPP

Cited by 4 publications

References 1 publication

The Efficiency of Radiation Shielding Made From Materials With High Atomic Number and Low Mass Density

The Efficiency of Radiation Shielding Made From Materials With High Atomic Number and Low Mass Density

EFFICIENCY OF COMBINED Fe AND Pb RADIATION SHIELD OF TRANSPORT CASKS FOR SNF TRANSPORTATION

Change in radiation characteristics outside the SNF storage container as an indicator of fuel rod cladding destruction

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