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Russia Research, Power, and Waste Research Facilities
Research Facilities Overview
Research Facilities Developments
 

Research Facility List (by location)
Research Facility List (alphabetically)
Research Facility List (Russian acronym with transliteration)
Research Facility Map
Table of Research Reactors
 



Russia: Reactors: Research: Gidropress Experimental Design Bureau (OKB GIDROPRESS) Russia: Gidropress Experimental Design Bureau (OKB Gidropress), also called Hydropress Experimental Design Bureau
Опытное конструкторское бюро "Гидропресс"
 (ОКБ "Гидропресс")

Gidropress Activities Critical/Subcritical Assemblies

LOCATION: Podolsk, Moscow Oblast
Address:  21 ulitsa Ordzhonikidze, Podolsk, Moscow Oblast 142103
Telephone:  (095) 137-9783
[Nuclear Business Directory (Moscow: IBR Corporation, 1995), p. 117.] {Entered 10/19/99 MLB}
Director and Chief Designer: Yu. G. Dargunov
[Nuclear Business Directory (Moscow: IBR Corporation, 2000), p. 138.]{updated 01/03/01DK}
ACTIVITIES:
OKB Gidropress is involved in research and design of VVER reactors, reactor components, and safety and control systems. Gidropress also designed steam generators for BN fast reactors.
[Nuclear Business Directory (Moscow: IBR Corporation, 2000), p. 138.]{updated 01/03/01DK}
 
CRITICAL/SUBCRITICAL ASSEMBLIES:
NAME: Low Pressure Seven-Assembly Hydrodynamic Test Facility
APPLICATION:  
This test facility is designed to conduct hydrodynamic and vibration studies of VVER-1000 reactor fuel assemblies. 
 
NAME: High-Pressure Seven-Assembly Hydrodynamic Test Facility
APPLICATION:
This facility is designed to test experimental and standard fuel assemblies and is also used for cooperative tests, including tests of safety systems with standard parameters.
 
NAME: VVER-440 Hot Test Facility
APPLICATION:  
This facility is designed to test experimental and standard drives of safety systems.  This facility also tests VVER-440 fuel assemblies.
 
NAME: VVER-1000 Hot Test Facility
APPLICATION: 
This facility is designed to test experimental and standard drives of safety systems.  This facility tests VVER-1000 and VVER-500 fuel assemblies.
 
NAME: Critical Heat Flow Test Facility
APPLICATION:  
This facility is designed to study heat exchange in VVER reactors.
[Nuclear Business Directory (Moscow: IBR Corporation, 2000), pp. 138-139.] {entered 11/17/00 DK}

 

Last updated 8 July 2004 

Comments or questions? Contact Kenley Butler at MIIS CNS: kenley.butlerATmiis.edu


CNSThis material is produced independently for NTI by the Center for Nonproliferation Studies at the Monterey Institute of International Studies and does not necessarily reflect the opinions of and has not been independently verified by NTI or its directors, officers, employees, agents. Copyright © 2002 by MIIS.

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