Category Archives: Springer Series in Materials Science

Hydride Compositions for a Neutron Moderator

Transition metal hydrides may be used as neutron moderators for small-scale highly stressed nuclear power installations (NPI) at higher temperatures [7, 35]. Zirconium hydride moderator blocks of NRE should provide structural integrity during thrust regime and remain chemically inert under bimodal power regime at power fluxes of 1-1.5kW/m3 at average temperatures of 570K and temperature gradients of ~110K across the […]

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Possible Methods for Increasing Bearing Capacity of Ceramics

Improving of bearing capacity of ceramics with a limited plasticity in a broad tem­perature range should be done taking into account operation parameters. For fuel elements of the first sections of the HRA operating in the brittle-damage temperature range, it is necessary first of all to decrease the defectiveness of ceramic using various hardening methods capable to elevate the strength. […]

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Outlook for Nuclear Rocket Engine Reactors

NRE reactors of different Nuclear Engine Power Installations (NEPI) based on tested technologies have actually no alternatives in deep space investigations with the help of unmanned space probes and piloted interplanetary devices [1]. The developments of NREs were stopped only temporarily because humankind could not afford to spend a huge amount of money for large-scale cosmic studies. It is most […]

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Thermodynamic and Structural Characteristics of Materials

Thermodynamic studies of the solid solutions of refractory compounds with uranium monocarbide were started at the RIPRA “Luch” when no data on the thermodynamic properties in the homogeneity region at high temperatures were available in the liter­ature. Only basic approaches for estimating thermodynamic properties were known. Structural and fuel materials of the reactor core are based on refractory zirconium and […]

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Radiation Resistance of the HRA Elements

The radiation estimation of fuel elements (FA) and structural materials resistance to irradiation damage implemented during tests in reactor IVG-1 [1] and at measure­ments of properties after irradiation. The neutron flux and test temperatures in special reactor loops varied within 1012-1015n/sm2s and 450-2,000K accordingly [2, 3]. The uranium burnout in FA at propulsion mode (PM) of NRER within 1 h […]

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Radiation Durability of Graphitic Materials

As the graphitic materials are used in the HIP, irradiation durability of some graphite was investigated, especially at high temperatures 1,400-1,700 K [12]. First of all, the shrinkage rate of graphite is the most interest. For many types of graphite (except the isotropic MPG-6 graphite based on noncalcined coke) at high irradiation tem­peratures from 1,400 to 1,700K in the interval […]

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Diffusion Characteristics

The statistical thermodynamic theory of three-component interstitial phases devel­oped at the institute and the established properties of diffusion-controlled processes [12] such as sintering, nitration, carbonizing treatment, and oxidation facilitated the optimization of technologies used in investigations. Diffusion processes have a significant impact on the HGA materials’ interaction with hydrogen, and on consol­idation of carbide powders [3]. Experimental diffusion data were […]

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