Research Institute for Atomic Reactors GNTs NIIAR

Dimitrovgrad, Russia

Research Institute for Atomic Reactors GNTs NIIAR

Dimitrovgrad, Russia

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Volkov B.Yu.,Halden Reactor Project HRP | Yakovlev V.V.,RAS Research Center Kurchatov Institute | Ryazantsev E.P.,RAS Research Center Kurchatov Institute | Kalygin V.V.,Research Institute for Atomic Reactors GNTs NIIAR | And 3 more authors.
Atomic Energy | Year: 2013

The results of experiments performed in the research reactors HBWR (Norway) and MIR (Dimitrovgrad, Russia) with different variants of pelleted uranium dioxide fuel used in VVER and manufactured by Elektrostal MSZ and PWR using a standard method are analyzed. The analysis of the experiments made possible to study the effect of microstructural parameters on the thermomechanical behavior of the experimental fuel elements with this type of fuel. The experimental data on the temperature, length of a fuel kernel, and gas pressure beneath the fuel-element cladding can be used to verify models and thermomechanical codes describing the behavior of VVER fuel elements. © 2013 Springer Science+Business Media New York.


Volkov B.Yu.,Halden Reactor Project HRP | Jenssen H.,Halden Reactor Project HRP | Ryazantsev E.P.,RAS Research Center Kurchatov Institute | Yakovlev V.V.,RAS Research Center Kurchatov Institute | And 4 more authors.
Atomic Energy | Year: 2013

The IFA-503.1 and -503.2 in-reactor experiments in the HBWR (Norway) are comparable to the microstructural studies of four types of VVER and PWR uranium dioxide fuel fabricated to standard specifications. On the basis of analysis, the radiation stability of VVER fuel as compared with PWR fuel isevaluated and a quantitative dependence of the effect of the initial submicron porosity on the thermoradiation densification of all experimental fuels is obtained. Data confirming a correlation between the radiation densification and a thermal test for dimensional stability are obtained for the fuels studied. Complex experimental studies made it possible to expand the database for verifying thermo-mechanical models and codes intended for predicting the behavior of high-burnup VVER. © 2013 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 (-710-5°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.


Lizin A.A.,Research Institute for Atomic Reactors GNTs NIIAR | Tomilin S.V.,Research Institute for Atomic Reactors GNTs NIIAR | Gnevashov O.E.,Research Institute for Atomic Reactors GNTs NIIAR | Gazizov R.K.,Research Institute for Atomic Reactors GNTs NIIAR | And 5 more authors.
Atomic Energy | Year: 2013

The results of measurements of the solubility of UF4 and ThF4 in the eutectic 46.5LiF-11.5NaF-42KF are presented. Isothermal saturation of the salt melt by the experimental compounds is used. The UF 4 and ThF4 solubility in the experimental salt system is experimentally shown to be high (45 and 41 mol. %, respectively, at 700 C) and temperature-dependent in the interval 550-700 C. © 2013 Springer Science+Business Media New York.


Lizin A.A.,Research Institute for Atomic Reactors GNTs NIIAR | Tomilin S.V.,Research Institute for Atomic Reactors GNTs NIIAR | Gnevashov O.E.,Research Institute for Atomic Reactors GNTs NIIAR | Gazizov R.K.,Research Institute for Atomic Reactors GNTs NIIAR | And 6 more authors.
Atomic Energy | Year: 2013

The temperature dependence of the PuF3, AmF3, CeF3, and NdF3 solubility in the eutectic 46.5LiF-11.5NaF-42KF was measured in the interval 550-700 C. Anhydrous plutonium, americium, cerium and neodymium trifluorides were synthesized. The method of isothermal saturation with dissolution of pressed PuF3, AmF3, CeF3, and NdF3 pellets in melt in an inert argon atmosphere was used for the measurements. It was found that the solubility of trifluorides is high and strongly dependent on the melt temperature. The following values of the solubility were found 700 C: PuF 3 30, AmF3 43, CeF3 32, and NdF3 37. © 2013 Springer Science+Business Media New York.


Demchenko N.F.,Research Institute for Atomic Reactors GNTs NIIAR | Minvaliev R.N.,Research Institute for Atomic Reactors GNTs NIIAR | Rogozhina I.V.,Research Institute for Atomic Reactors GNTs NIIAR | Salikov M.M.,Research Institute for Atomic Reactors GNTs NIIAR | Shipilov V.I.,Research Institute for Atomic Reactors GNTs NIIAR
Measurement Techniques | Year: 2011

Two basic methods for measuring exposure dose capacity (EDC) and of determining the activity of gammaradiation sources based on the radionuclide 60Co are considered, namely, direct measurements and relative measurements (the comparator method), and also a system for transferring the dimensions of the units of EDC and its equivalent activity from measuring instruments of the 1st category to commercial sources of the 3rd category. © 2011 Springer Science+Business Media, Inc.


Zhemkov I.Yu.,Research Institute for Atomic Reactors GNTs NIIAR | Izhutov A.L.,Research Institute for Atomic Reactors GNTs NIIAR | Novoselov A.E.,Research Institute for Atomic Reactors GNTs NIIAR | Poglyad N.S.,Research Institute for Atomic Reactors GNTs NIIAR | Svyatkin M.N.,Research Institute for Atomic Reactors GNTs NIIAR
Atomic Energy | Year: 2014

A large volume of experimental research is being done in BOR-60 to validate promising new nuclear materials and increase fuel burnup and neutron fluence. Service life tests in reactors are time-consuming. It is obvious that they cannot be done in BOR-60 over the time to its final shutdown. The continuation of the irradiation programs in MBIR will make it possible to start up new reactors and validate the possibility of extending the service life of operating reactors. Research has shown that the irradiation of materials started in BOR-60 can be continued in MBIR. © 2014 Springer Science+Business Media New York.


Toporova V.G.,Research Institute for Atomic Reactors GNTs NIIAR | Petelin A.L.,Research Institute for Atomic Reactors GNTs NIIAR
Atomic Energy | Year: 2011

Coolant consumption, which is possible in the irradiation channels of the reflector of an SM reactor with a pressure drop of 5-50 kPa, is studied computationally and experimentally. The computed coolant consumption per channel agrees well with that measured in a retort a channel simulator. It is shown that targets can be irradiated with transuranium elements in the reflector channels, which are not specially designed for this purpose. The admissible thermal power on the target for 72 mm in diameter channels is 16 and 30 kW with pressure differential 5 and 42 kPa, respectively. The temperature margin of the target cladding to saturation temperature is at least 25C, and the kernel temperature is at least to 90C the melting temperature. © 2011 Springer Science+Business Media, Inc.


Kursky A.S.,Research Institute for Atomic Reactors GNTs NIIAR | Kalygin V.V.,Research Institute for Atomic Reactors GNTs NIIAR | Semidotsky I.I.,Research Institute for Atomic Reactors GNTs NIIAR | Mikhajlov P.A.,Research Institute for Atomic Reactors GNTs NIIAR
Atomic Energy | Year: 2013

The radiation and explosion safety of water-moderated and -cooled reactors in regimes with steam discharged through safety valves is described. It shown for the VK-50 boiling-water reactor that diverting the steam after the safety valves to outside the protective shell minimizes the consequences of emergencies during planned hydrogen discharges into the atmosphere and guarantees localization of the radionuclides. © 2013 Springer Science+Business Media New York.


Demchenko N.F.,Research Institute for Atomic Reactors GNTs NIIAR | Minvaliev R.N.,Research Institute for Atomic Reactors GNTs NIIAR | Shipilov V.I.,Research Institute for Atomic Reactors GNTs NIIAR | Kharitonov I.A.,Mendeleev Institute for Metrology
Measurement Techniques | Year: 2012

A method for the estimation of the contribution of photon radiation to the detector readings for measurement of the exposure dose rate and the equivalent activity of neutron sources with the use of bismuth screens and filters is considered. The exposure dose rate of the photon radiation is determined by the signal-comparison method. ©2012 Springer Science+Business Media, Inc.

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