Untitled

Tsykanov, V. A.; Klinov, A. V.; Starkov, V.A.; Pimenov, V.V.; Chertkov, Yu.B.

doi:10.1023/a:1021763815423

Cited by 10 publications

(2 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…[11] This process complies with the general rules of isotope accumulation in the nuclear reactor. In particular, in the course of irradiation, the concentration of the Figure 2.…”

supporting

confidence: 67%

Highly Enriched Nickel‐63 Radionuclide for β‐Voltaic Nuclear Batteries

Bryskin¹,

Пустовалов²,

Tsvetkov³

et al. 2014

Energy Tech

View full text Add to dashboard Cite

The requirements for nickel‐63 (Ni‐63) in β‐voltaic nuclear batteries were analyzed. For commercial use, the degree of Ni‐63 enrichment should in the range of 70–90 % instead of the currently available commercial product (18–20 % enrichment). Such a significant increase in the enrichment level would improve the energy conversion efficiency of the β‐particles by ten times. An industrial scheme for production of highly enriched Ni‐63 is proposed.

show abstract

“…[11] This process complies with the general rules of isotope accumulation in the nuclear reactor. In particular, in the course of irradiation, the concentration of the Figure 2.…”

supporting

confidence: 67%

Highly Enriched Nickel‐63 Radionuclide for β‐Voltaic Nuclear Batteries

Bryskin¹,

Пустовалов²,

Tsvetkov³

et al. 2014

Energy Tech

View full text Add to dashboard Cite

show abstract

“…Due to the high cost of enrichment, it is possible to produce a relatively small (up to 4.5 kg) amount of enriched chromium. The preliminary estimates have shown that the required values of the specific activity of 51 Cr (about 1 kCi/g) can be achieved only in the most high-flux region of the SM-3 reactor: the central neutron trap [10].…”

Section: Introductionmentioning

confidence: 99%

Production of the artificial ⁵¹Cr neutrino source in the BEST project

et al. 2022

View full text Add to dashboard Cite

The production of the artificial 51Cr neutrino source with activity > 3 MCi for the experiment BEST is presented. This procedure consisted of making a 50Cr target and irradiating it with thermal neutrons in a nuclear reactor SM-3. The production of a target in the form of disks with a thickness of 4 mm and a diameter of 84 and 88 mm included enrichment (to 96.5% in 50Cr) of natural chromium in the form of oxyfluoride by gas centrifugation, electrolytic reduction and refining of metallic chromium, as well as the formation of chromium disks by spark plasma sintering. Simulations of various source geometries, neutron flux and nuclear transmutation were carried out to validate the design of the source, the irradiation device and the transport container, the required chemical purity of the target and the irradiation schedule in the reactor. The calculated activity of the source after 75 effective days of irradiation was 3.55 MCi. The activity of the source was measured by the calorimetric method and amounted to 3.41 MCi at the time of its delivery to the Baksan Neutrino Observatory. This is the most intense chemically pure neutrino source ever produced.

show abstract

Upgrading the Design of Cruciform Fuel Elements to Increase their Heat-Engineering Characteristics

2005

View full text Add to dashboard Cite

The change occurring in the heat-engineering characteristics of a cruciform fuel element in a SM reactor as a result of the change in the characteristic dimensions of the fuel element, such as the diameter of the circumscribing circle, the indentation radius, and the rounding radius of a lobe, and as a result of the presence of a central displacer in the element is examined. The optimal values of the indentation radius and rounding radius of a lobe are determined to be 0.5 mm. It is shown that the presence of a central displacer in a fuel element substantially decreases the maximum temperature of the kernel and decreases the coefficient of nonuniformity of the heat flux density. For the same maximum kernel temperature in a standard fuel element and a fuel element with a displacer, the maximum heat flux density in the latter element gives an additional margin up to the crisis of heat transfer.To achieve fast-neutron flux densities above 2·10 15 sec -1 ·cm -2 in high-flux reactors and booster converters, it is necessary to develop fuel elements which can operate at high temperatures and under large heat loads. At present, the most promising fuel element is the SM reactor fuel element, which has proven itself with heat flux density (average over the perimeter) 15 MW/m 2 , maximum fuel kernel temperature 500-550°C, and burnup up to 60% [1].The purpose of the present work is to search for ways to upgrade the standard fuel element of a SM reactor to improve the admissable heat flux density while maintaining or decreasing the maximum temperature of the fuel composition.A cruciform fuel element is characterized by the diameter of the circumscribing circle (d cd ), the indentation radius (r ind ), and the rounding radius of a lobe (r L ) (Fig.

show abstract

Untitled

Cited by 10 publications

References 0 publications

Highly Enriched Nickel‐63 Radionuclide for β‐Voltaic Nuclear Batteries

Highly Enriched Nickel‐63 Radionuclide for β‐Voltaic Nuclear Batteries

Production of the artificial ⁵¹Cr neutrino source in the BEST project

Upgrading the Design of Cruciform Fuel Elements to Increase their Heat-Engineering Characteristics

Contact Info

Product

Resources

About

Untitled

Cited by 10 publications

References 0 publications

Highly Enriched Nickel‐63 Radionuclide for β‐Voltaic Nuclear Batteries

Highly Enriched Nickel‐63 Radionuclide for β‐Voltaic Nuclear Batteries

Production of the artificial 51Cr neutrino source in the BEST project

Upgrading the Design of Cruciform Fuel Elements to Increase their Heat-Engineering Characteristics

Contact Info

Product

Resources

About

Production of the artificial ⁵¹Cr neutrino source in the BEST project