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Novovoronezh, Russia

Vitkovskii I.L.,Branch of Rosenergoatom Concern | Nikonov S.P.,RAS Research Center Kurchatov Institute | Ryasnyi S.I.,National Research University Moscow Power Engineering Institute
Thermal Engineering (English translation of Teploenergetika) | Year: 2014

The subject of this paper is a transient caused by connection of a standby loop to three operating circulation pumps at the initial reactor heat rate equal to 70% of the rated value without preliminarily reducing it to 30% of the rated level as required by the safe operation regulations. Failure of the following normal operation systems is supposed: the first- and the second-type warning protection systems, all quick-acting reducing devices releasing steam into the auxiliary manifold, the electric heaters of the pressurizer, the pressurizer injection system, the primary cooling circuit fluid makeup/blow-through systems, and the blocking systems to shut down the main circulation pump after the level in the steam generator is exceeded. In addition, it is supposed that, under transient conditions, the valves of the turbine regulation system will be in the position in which they were at the moment of the initial event until generation of the signal for positive closing of the turbine stop valves. The first signal to actuate the reactor emergency protection system (EPS) is skipped. The failure of all quick-acting reducing devices releasing steam into the atmosphere is assumed. In addition to equipment failure, at the moment when the main circulation pump is connected, the operator erroneously puts in a new setting to maintain the power allowable for four pumps in operation-in the calculations it was taken equal to 104% of the rated level at most considering the accuracy of evaluating and maintaining the reactor heat rate-and the working group of the reactor protection and control system (P&CS) starts moving upward. On reaching the set power level, the automatic reactor power regulator stops operating and the P&CS elements remain in the position in which they are at the moment. Compliance with the design safety criteria for the adopted scenario of the transient is demonstrated. © 2014 Pleiades Publishing, Inc. Source


Terekhov D.V.,Branch of Rosenergoatom Concern | Dunaev V.I.,ZAO Diakont
Thermal Engineering (English translation of Teploenergetika) | Year: 2014

The calculation of safety parameters was carried out in the process of upgrading the fuel-handling machine (FHM) of the Novovoronezh nuclear power plant (NPP) unit no. 5 based on the results of quantitative safety analysis of nuclear fuel transfer operations using a dynamic logical-and-probabilistic model of the processing procedure. Specific engineering and design concepts that made it possible to reduce the probability of damaging the fuel assemblies (FAs) when performing various technological operations by an order of magnitude and introduce more flexible algorithms into the modernized FHM control system were developed. The results of pilot operation during two refueling campaigns prove that the total reactor shutdown time is lowered. © 2014 Pleiades Publishing, Inc. Source


Kucherenko O.V.,Branch of Rosenergoatom Concern | Shvarov V.A.,Branch of Rosenergoatom Concern
Thermal Engineering (English translation of Teploenergetika) | Year: 2014

Reliability of steam generators depends not only on the main technical characteristics and correctness of the operational mode but also on the cleanliness of the heat-exchange surface and the presence of slime precipitated on the bottom. To provide the cleanliness, chemical methods of cleaning the heatexchange surfaces are used. In this article, we consider the process of removal of sediments that are formed precisely on the bottom of the steam generator from its volume. Possible mechanical methods for removal of sediments are presented. The consideration of variants of cleaning approved for acting steam generators showed the efficiency and applicability of the developed installation for the slime removal from steam generators. The main principles of construction of the system for slime removal from the steam generator bottom and constructive features of the installation, which make it possible to implement the stated tasks on the slime removal from the steam generator bottom, are given. © 2014 Pleiades Publishing, Inc. Source


Rosnovskii S.V.,Branch of Rosenergoatom Concern | Bulka S.K.,Branch of Rosenergoatom Concern
Thermal Engineering (English translation of Teploenergetika) | Year: 2014

An original technology for the conditioning of solidified radioactive waste was developed by the Novovoronezh nuclear power plant (NPP) staff. The technology provides for waste placement inside NZK-150-1.5P containers with their further storage at light hangar-type storage facilities. A number of technical solutions were developed that allow for reducing the gamma-radiation dose rate from the package formed. A methodology for prediction of the radiation situation around hangars, depending on the radiation characteristics of irrecoverable shielding containers (ISCs) located in the peripheral row of a storage facility, was developed with the purpose of assuring safe storage. Based on empirical data, the field background gamma-radiation dose rate at an area as a function of the average dose rate at the hangar surface and the average dose rate close packages, placed in the peripheral row of the storage facility, was calculated. The application of the developed methodology made it possible to reduce by ten times the expenditures for the conditioning and holding of solidified radioactive waste (SRW) while unconditionally providing storage safety. © 2014 Pleiades Publishing, Inc. Source


Moiseev A.V.,RAS Institute for Physics and Power Engineering | Khomyakov Yu.S.,RAS Institute for Physics and Power Engineering | Semenov M.Yu.,RAS Institute for Physics and Power Engineering | Seregin A.S.,RAS Institute for Physics and Power Engineering | And 8 more authors.
International Conference on the Physics of Reactors 2010, PHYSOR 2010 | Year: 2010

Reactivity balance is a key element for nuclear safety substantiation for reactor facilities of any type. Commercial operation of BN-600 power fast reactor in Beloyarsk NPP stimulated work on finding optimal balance between conservative safety margins and reactor performance. This paper is devoted to the studies on the possibility of achieving high indices on the accuracy of reactivity balance justification. It is described calculation and experimental methods for determination of components of BN-600 reactivity balance. Results of comparison calculation and experimental data are presented. Taking into account experimental data and verification of codes facilitates increase of accuracy of max excess reactivity forecast up to 0.2%Δk/k. Forecast of the BN-600 reactor core subcriticality after SR setting can be made to the accuracy of 0.2-0.4%Δk/k, accuracy of SHR system worth forecast is 7%, single SR and reactor safety system 7-8%. These values make it possible to significantly decrease (by a factor of 2) conservatism of evaluation of these parameters justifying nuclear safety of the BN-600 reactor core. Source

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