Achievements diagram

2013	The experiments on definition of dynamic characteristics of repaired graphite columns using vibration load method were carried out	TKR Test Facility
	The complex of works ensuring experiments aimed on justification of alternative technology of reactor plant components’ lifetime parameters restoration (wide cutting) was carried out.	TKR Test Facility
	The complex of works performed at TKR Test Facility on preparation and performing of tests of facilities and tools to restore the lifetime parameters of RBMK-1000 elements was carried out. The experimental investigations of influences of graphite columns deformation after their restoration, onto rigidity and dynamic characteristics (natural frequencies, vibration decrement) of fuel channels cells and Monitoring and Control System’s channels were performed.	TKR Test Facility
	Acceptance tests of a head specimen of the heat exchanger for the 4th unit of Rostov NPP were carried out.	Heat Exchange Test Facility
	The experimental-calculated investigations aimed on justification of thermo-technical reliability (critical heat flux margin) of FA operation in RBMK-1000 fuel channel of increased diameter, taking into account cells curving occurring during additional lifetime, were performed.	PSB RBMK Test Facility
2012	The experimental part of TACIS project R2.01/06 «Development of measures towards modernization of water chemistry monitoring systems for 1st and 2nd circuits of Kalinin NPP Units 1&2» was performed.	V-3 Test Facility
2012	The experimental-calculated investigations of consequences of engagement of telescopic interconnection tracks (TIT) of RBMK graphite column were carried out.	TKR Test Facility
2011	The experiment on investigation of passive systems (GE-2 and PHRS) influence on temperature state of fuel elements in cold leg SBLOCA was carried out.	PSB-VVER Test Facility
2011	An experimental investigation for Codes verification by accounts of nonuniformity of steam load at increased capacity of steam generators was performed.	V-3 Test Facility
2010	The experiment on investigation of temperature state of fuel element’s cladding during double-ended cold leg break with operation of all passive safety systems (including GE-2 and PHRS) and loss of all power supply was performed.	PSB-VVER Test Facility
2010	The work on experimental (test bench) tests of hydraulic characteristics of VVER-440 FA models of the third generation (RK-3) was performed. Different fixing techniques of fuel elements were used. The water flow rate during the experiments was up to 150 m3/h.	Filter-1 Test Facility
2009	The third full-scale experiment with the central fuel channel break at rated coolant parameters (so-called «brittle» rupture) was carried out.	TKR Test Facility
	Comparison tests of alternative ADF for FA of VVER-1000 at water flow rate up to 550 m3/h were carried out. The ADF were designed by OKB «Gidropress», «Afrikantov OKBM and JSC «MSZ».	Filter-1 Test Facility
	An experiments aimed on investigations of the following emergency states of RBMK-1000 reactor were performed: Reducing of the flow rate in one GDH because of mechanic filter's damage in the inlet of GDH; Cooling of reactor core in natural circulation condition in case of loss of auxiliary power supply; A Steam-line rupture разрыв occurring outside the compartments of accident localization system in case of loss of Unit’s auxiliary power supply; Downcomer rupture; Double-ended rupture of the pressure header; Double-ended rupture of GDH after check valve with the adjacent GDH's check valve failure; Double-ended rupture of GDH before check valve; Double-ended rupture of GDH after check valve.	PSB RBMK Test Facility
2008	An experimental investigation of the accident with double-ended break of main circulation pipeline at the entrance to reactor was performed. Unique experimental data for verification of the Codes used in VVER emergency situation analysis (including NPP-2006) were obtained.	PSB-VVER Test Facility
2006	An experimental investigation of the influence of new passive safety systems GE-2 and PHRS (The Project «NPP-2006») on the thermal state of fuel elements at hot leg double-ended rupture (2х100%). Two experiments (the second one was on the recurrence) were carried out. Duration of the experiments was 24 hours each one.	PSB-VVER Test Facility
	The thermal-hydraulics and thermo-cyclic tests of the full-scale model of steam generator by DOOSAN Company (South Korea) were performed. In 2009 the second phase of this work was carried out.	Heat-exchange Test Facility
	The investigations of the effectiveness of ADF of different designs developed by OKB «Gidropress», JSC «MSZ» and MEPhI for VVER-440 FA (22 designs in total) on anti-debris efficiency, hydraulic resistance, strength, influence on the field of coolant velocities in FA were carried out.	Filter-1 Test Facility
2005	15 experiments within the TACIS R2.03/97 Project were carried out. The project was dedicated to the development and verification of accidents management procedures for VVER-1000 NPP.	PSB-VVER Test Facility
	The second full-scale experiment with overheating and rupturing of central emergency channel in graphite stack of the MRS was performed.	TKR Test Facility
	Two experiments on investigation of dynamic steam-water jets and shock waves effects on the equipment in case of pipeline breaks at NPPs were performed.	Test-facility-model of accident localization system
2004	The experiment «Cold leg leak 4,1%» that was comparative to the one carried out at LOBI integral test facility(Italy) was performed.	PSB-VVER Test Facility
2004	The first experiment at overheating and emergency channel's break at the center of graphite stack that contains 25 graphite columns with fuel channels was performed.	TKR Test Facility
2003	2 experiments were performed: 2-phase natural circulation (stepwise primary circuit draining); loss of coolant (simulation of emergency conditions of Kozloduy NPP, 1996 г.).	PSB-VVER Test Facility
	6 experiments were conducted in the frame of the Tacis Project R2.01/99. The Project was devoted to the experimental qualification of bubble-condenser system of accident localization system of Kola NPP Unit 3	Test-facility-model of accident localization system
	An experimental program was conducted under the contract with IRSN (France) aimed on investigation of the processes of the debris’s transfer and deposition. The program was also devoted to pressure decrease in relation to the French PWR reactors.	VITRA Test Facility
2002	Five experiments were carried out. 1. Coolant leak from the outlet chamber of reactor model; 2. Cold leg coolant leak; 3. Double-ended hot leg break (2х25%); 4.Loss of four MCP; 5. Loss of one MCP.	PSB-VVER Test Facility
2002	The experimental investigations were performed as follows: under an agreement with GRS (Germany), two experiments aimed on investigation of VVER-440/V-213 bubble-condenser system operation under steam-line break were carried out; under the contract with Paksh NPP (Hungary), three experiments modeling VVER-440/V-213 bubble-condenser system operation under accidents at NPPs were carried out; main steam-line break; primary circuit leak with the equivalent diameter of 200 mm; primary circuit leak with the equivalent diameter of 90 mm.	Test-facility-model of accident localization system
2001	The experimental investigations were performed as follows: 1. Primary to secondary leaks (1,4%); 2. Cold leg break 2,4 %; 3. Cold leg break 11%; 4. Cold leg break 16%; 5. Collecting chamber leakage 11%; 6. SG steam line break.	PSB-VVER Test Facility
1999	13 experiments with loss of coolant from different points of primary circuit were carried out. An influence of size and placement of leakage as well as different emergency cooling system failures on the accident progress were investigated.	PSB-VVER Test Facility
1999	The experimental program of TACIS/PHARE No. PH2.13/95 «Bubble Condenser Experimental Qualification Project» on modeling of VVER-440/V-213 Bubble Condenser System operation in DBA (double-ended cold leg rupture) was carried out.	Test-facility-model of accident localization system