Some distinctive features of alloys of the sodium-potassium-cesium system

Kazachkovskii, O. D.; Starkov, A. V.; Кочеткова, Е. А.; Bogdanovich, N. G.; Sulim, E. V.; Levchenko, V. E.; Lyubchenko, N. F.; Zharinov, V. I.

doi:10.1007/bf00761445

Cited by 6 publications

(6 citation statements)

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“…"NaKCs alloys with a certain content of components are capable of oxidizing in air at 300-1000 K without intensive release of aerosols and a noticeable increase in temperature" [48]. Eutectic alloy NaKCs does not ignite in the temperature range 293 ... 973 K [45].…”

Section: Alternative Coolants Sodium Potassium and Cesium Alloysmentioning

confidence: 99%

“…When analyzing three-component systems (liquid alloys), appropriately delineated triangles are used (they are called Gibbs-Rosebohm triangles or Rosebohm triangles). On such a triangle for the NaKCs alloy, it is possible to distinguish the concentration range corresponding to the non-flammability of the alloy [48]. The boundary of the region is determined by the equation of an ellipse with the ratio of the semi axes 2.4 m center at the point corresponding to an alloy close to eutectic [48].…”

Section: Alternative Coolants Sodium Potassium and Cesium Alloysmentioning

confidence: 99%

“…On such a triangle for the NaKCs alloy, it is possible to distinguish the concentration range corresponding to the non-flammability of the alloy [48]. The boundary of the region is determined by the equation of an ellipse with the ratio of the semi axes 2.4 m center at the point corresponding to an alloy close to eutectic [48].…”

Section: Alternative Coolants Sodium Potassium and Cesium Alloysmentioning

confidence: 99%

“…The center of the ellipse is determined by the content of sodium 12% (at. ), potassium 44%, cesium 44% (or the mass content of 3.52% Na -21.88% K -74.60% Cs) [48]. The boundaries of the non-flammable range (% at.…”

Section: Alternative Coolants Sodium Potassium and Cesium Alloysmentioning

confidence: 99%

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Physics behind the Concept of a Sodium-Potassium-Cesium-Cooled Martian Nuclear Reactor

Sergeevich¹

2022

Adv. sci. technol. eng. syst. j.

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The main goal of the work is to determine the basic conceptual solutions of a nuclear reactor operating on the surface of another planet. The problem was solved using the example of the Martian nuclear power plant. The article uses calculation and optimization research methods and corresponding program codes (well-known and author's). The results of the study made it possible to formulate the basic requirements for the Martian nuclear power plant and select the type of reactor. This is a new type of reactor: pressurized liquid metal fast reactor. It is proposed to use an innovative cermets nuclear fuel based on mixed mononitride and uranium metal nanopowder, which was previously considered by the author for new generation BN and BREST ground-based reactors. It is proposed to use a eutectic (or near-eutectic) NaKCs alloy as a coolant. Optimization of the alloy composition has been carried out. The fuel and coolant of the reactor contains long-lived radioactive waste to be transmuted. NaKCs alloy is less reactive than pure alkali metals including Na, K and Cs. With an electric power of 600 MW, it is possible to ensure the internal self-protection of the reactor. All emergency modes of the ATWS type (anticipated transient without scram) are not hazardous. This means that with a decrease in power to values characteristic of the initial stages of the colonization of Mars, the safety of the reactor is easily ensured. The relatively low chemical activity of the coolant makes it possible to use a two-circuit energy conversion scheme. The second circuit can use water or carbon dioxide. Carbon dioxide is preferred because of its presence in the atmosphere of Mars (95% CO2). The significance of the research lies in the possibility of constructing a Martian nuclear power plant within the framework of existing technologies.

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Section: Alternative Coolants Sodium Potassium and Cesium Alloysmentioning

confidence: 99%

Section: Alternative Coolants Sodium Potassium and Cesium Alloysmentioning

confidence: 99%

Section: Alternative Coolants Sodium Potassium and Cesium Alloysmentioning

confidence: 99%

Section: Alternative Coolants Sodium Potassium and Cesium Alloysmentioning

confidence: 99%

See 2 more Smart Citations

Physics behind the Concept of a Sodium-Potassium-Cesium-Cooled Martian Nuclear Reactor

Sergeevich¹

2022

Adv. sci. technol. eng. syst. j.

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“…By now, multicomponent metallic alloys with record breaking low melting temperatures, e.g., near eutectic compositions of alloys of the ternary Na-K-Cs system (-78°С) and others [1,2], are known. In this connection, an urgent problem is to create devices and units for determining physical-chemical properties of liquid metal melts under low temperature experi mental conditions [3].…”

Section: Introductionmentioning

confidence: 99%

A combined device for the joint study of the surface tensions and electron work functions of liquid-metal melts at low temperatures

et al. 2014

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The design and test data of the combined device, which is intended to simultaneously measure the surface tensions and electron work functions of metals and alloys in static high vacuum conditions in a tem perature range of 60-400 K, are given. The measurements of the electron work function of pure Na, K, Rb, and Cs and near eutectic alloys of the ternary Na-K-Cs system showed high reliability and accuracy of the obtained data.

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Use of the alloy Na−K−Cs as a coolant in a fast reactor: Preliminary results of safety characteristics optimization

Kuz'min¹,

Okunev²

2000

At Energy

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Some distinctive features of alloys of the sodium-potassium-cesium system

Cited by 6 publications

References 0 publications

Physics behind the Concept of a Sodium-Potassium-Cesium-Cooled Martian Nuclear Reactor

Physics behind the Concept of a Sodium-Potassium-Cesium-Cooled Martian Nuclear Reactor

A combined device for the joint study of the surface tensions and electron work functions of liquid-metal melts at low temperatures

Use of the alloy Na−K−Cs as a coolant in a fast reactor: Preliminary results of safety characteristics optimization

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