State Science Center Research Institute for Atomic Reactors s

Dimitrovgrad, Russia

State Science Center Research Institute for Atomic Reactors s

Dimitrovgrad, Russia
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Akulinichev S.V.,RAS Institute for Nuclear Research | Artamonov S.A.,RAS Institute for Nuclear Research | Tychkin I.S.,RAS Institute for Nuclear Research | Chaushanskii S.A.,RAS Institute for Nuclear Research | And 4 more authors.
Atomic Energy | Year: 2017

The conditions for the irradiation of 168Yb-enriched samples in reactors for obtaining sources to be used in brachytherapy are examined. The optimum irradiation conditions in the SM-3 high-flux reactor are determined. The computational methods are compared with the measurements. © 2017 Springer Science+Business Media New York


Ignatiev V.V.,RAS Research Center Kurchatov Institute | Feynberg O.S.,RAS Research Center Kurchatov Institute | Zagnitko A.V.,RAS Research Center Kurchatov Institute | Merzlyakov A.V.,RAS Research Center Kurchatov Institute | And 6 more authors.
Atomic Energy | Year: 2012

The possibilities of competitive development of a liquid-salt reactor with a cavity-type core for developing thorium-uranium breeder reactor and for burning transuranium elements from the spent fuel of power reactors are described. Such a reactor is characterized by fuel-cycle flexibility, since it is capable of operating with a wide spectrum of fuel and raw-materials loads without being stopped or structurally altered. Compared with thermal liquid-salt reactors with a graphite moderator, these reactors have deeply negative temperature coefficients of reactivity (-7·10 -5°C -1), and the fuel salt is completely processed in 3-4 years. Such a reactor facility can be incorporated into any strategy for the development of nuclear power. © 2012 Springer Science+Business Media, Inc.


Gil'mutdinov I.F.,State Science Center Research Institute for Atomic Reactors s | Shishin V.Y.,State Science Center Research Institute for Atomic Reactors s | Starkov V.A.,State Science Center Research Institute for Atomic Reactors s | Fedoseev V.E.,State Science Center Research Institute for Atomic Reactors s | And 3 more authors.
Atomic Energy | Year: 2015

A variant of experimental dispersion fuel elements with fuel based on uranium dioxide as fissile material in a silumin matrix, which have been proposed for modernizing the core of the SM reactor and are irradiated in a wide spectrum of neutron-physical and thermophysical parameters in the reflector channel of the reactor, is investigated. A nonuniformity with fuel density two times higher than the average over a fuel element, viz., a cluster of uranium dioxide particles in the central zone of the kernel, has been found in the distribution of the fuel phase in the fuel elements. The thermophysical calculations show that for such a distribution of fuel particles the temperature of the fuel composition with heat flux density from the fuel-element surface >6 MW/m2 can reach the melting temperature of the matrix. This is confirmed by investigations of fuel elements with appreciably larger volume and shape change. To increase the serviceability of the fuel elements, ways of improving their design and the material composition of the fuel mix are proposed. © 2015 Springer Science+Business Media New York


Pavlov S.V.,State Science Center Research Institute for Atomic Reactors s
Atomic Energy | Year: 2011

The effect of fuel burnup in VVER-1000 fuel elements on the utilization effectiveness of ultrasonic detection of leaky fuel elements is examined. It is determined that the limitations of this method are due to the interaction of fuel-element cladding with the fuel pellets. Threshold for fuel burnup in VVER-1000 fuel elements with E-110 alloy cladding, determining the application limits of ultrasonic detection of leaky fuel elements in fuel assemblies, is determined. © 2011 Springer Science+Business Media, Inc.


Toporova V.G.,State Science Center Research Institute for Atomic Reactors s | Pimenov V.V.,State Science Center Research Institute for Atomic Reactors s | Risovanyi V.D.,State Science Center Research Institute for Atomic Reactors s | Zakharov A.V.,State Science Center Research Institute for Atomic Reactors s
Atomic Energy | Year: 2011

Models of absorbing elements with a promising material for the control organs of nuclear reactors have been tested in the SM reactor-pelleted and powder kernels with different composition based on dysprosium hafnate in a mixture with boron carbide. The neutron fluence with energy>0.1 MeV averaged over a kernel volume was (0.9-1.3).1022 cm -2 at the moment the tests were completed for different samples. The temperature at the center of the kernels of the absorber element models during irradiation was 620-1100°C in channel No. 4 and 400-500°C in channel No. 9. The results of the materials science studies show that on the whole the serviceability of the absorbing elements based on pellets and powders of dysprosium hafnate is high. © 2011 Springer Science+Business Media, Inc.


Gataullina G.D.,State Science Center Research Institute for Atomic Reactors s | Uzikov V.A.,State Science Center Research Institute for Atomic Reactors s | Osipova T.A.,State Science Center Research Institute for Atomic Reactors s
Atomic Energy | Year: 2013

Understating natural intercellular circulation in the core during fault situations and transitional regimes results in suboptimal designs of pool reactors. For RBT reactors at the Research Institute of Nuclear Reactors, it is shown that instead of using structure elements specially intended for organizing a natural circulation loop the natural intercellular circulation can be fully taken into account. In addition, these structural elements themselves carry additional failure-associated risks. The results of a computational analysis of the development of pre-accident situations associated with the disruption of forced circulation of coolant through an RBT core and equipment failure are presented. © 2013 Springer Science+Business Media New York.


Kurskii A.S.,State Science Center Research Institute for Atomic Reactors s | Eshcherkin V.M.,State Science Center Research Institute for Atomic Reactors s | Kalygin V.V.,State Science Center Research Institute for Atomic Reactors s | Svyatkin M.N.,State Science Center Research Institute for Atomic Reactors s | Semidotskii I.I.,State Science Center Research Institute for Atomic Reactors s
Atomic Energy | Year: 2012

The thermal and economic performance indices of a present-day low-capacity reactor facility with a boiling-water vessel reactor are presented. The operation of a reactor with natural coolant circulation is highly reliable in different operating regimes of a nuclear heat and power plant. © 2012 Springer Science+Business Media, Inc.


Kosenkov V.M.,State Science Center Research Institute for Atomic Reactors s | Posevin A.O.,State Science Center Research Institute for Atomic Reactors s | Silantiev P.P.,State Science Center Research Institute for Atomic Reactors s
Atomic Energy | Year: 2012

Experimental data are presented on the change of the pycnometric density and unit-cell volume of beryllium irradiated in an SM reactor to neutron fluence 14·10 22 cm -2. The behavior of the unit-cell volume as a function of the neutron fluence is similar to the data for other metals. This and data on the volume change in beryllium oxide, where a large amount of gas is also formed during irradiation, make it possible to evaluate critically the assertion that helium forms a solid substitution solution. It is proposed that helium is confined in small accumulations. © 2012 Springer Science+Business Media, Inc.


Demchenko N.F.,State Science Center Research Institute for Atomic Reactors s | Kuznetsov R.A.,State Science Center Research Institute for Atomic Reactors s | Shipilov V.I.,State Science Center Research Institute for Atomic Reactors s | Moiseev N.N.,Mendeleev Institute for Metrology | Kharitonov I.A.,Mendeleev Institute for Metrology
Measurement Techniques | Year: 2014

Specialized gamma-spectrometry equipment is considered and the metrological characteristics of the instrument spectrum are investigated on practical sources of ionizing radiation. © 2014 Springer Science+Business Media New York.


Kuzin M.A.,State Science Center Research Institute for Atomic Reactors s
Chemical and Petroleum Engineering | Year: 2010

A model of a centrifuge is developed, critical centrifuge speeds are determined by the Dunkerley and Krylov method, and the expected endurance with centrifuge vibration is determined. © 2010 Springer Science+Business Media, Inc.

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