VR-1 – Training Reactor for Research Activities (WCZV)
Core Data
Hosting Legal Entity
Czech Technical University in Prague
V Holešovičkách 2, Training Reactor VR-1, Prague, PO: Prague 8, 180 00 (Czech Republic)
Type Of RI
Coordinating Country
Czech Republic
Current Status:
Operational since 1990
Scientific Description
Mission and objectives
The training reactor VR-1 Sparrow is a lightwater reactor aimed mainly at education and training of students as well as specialists from the nuclear field. The reactor is situated in the heart of Europe, close to the Prague city centre, the capital city of the Czech Republic.The operation and maintenance of the reactor is in the gestion of the Department of Nuclear Reactors. The reactor firstly reached criticality in late 1990. During past decades it became one of the pillars of nuclear education in the Czech Republic. International collaboration became an important part of the reactor activities. Thanks to the reactor variable design it can be used for various different tasks including testing of new measuring equipment or demonstrating the basics of neutron imaging.

RI Keywords
Nuclear training centre, Nuclear reactor
RI Category
Nuclear Research Facilities
Scientific Domain
Physics, Astronomy, Astrophysics and Mathematics
ESFRI Domain
Physical Sciences and Engineering
VR-1 Training Reactor

The training reactor VR-1 is a light water, zero power research reactor with enriched uranium. Its design satisfies the requirement of easy accessibility to the reactor core with respect to education students and training qualified staff for nuclear industry. The pool type arrangement assures quick and easy access to the reactor core, easy insertion and extraction of various experimental samples and detectors, simple and safe manipulation with fuel elements. Light water, used at the same time as the moderator, reflector and coolant, functions also as biological shielding, which enables access to the reactor during operation. Because of its low power there is sufficient natural flow to take away the heat released by the fission of uranium in the reactor core without a pump, which has been installed anyway, to ensure better flow of water around fuel element tubes to prevent deposit formation on the fuel surface. The Reactor is operated at an atmospheric pressure at a temperature of about 20 °C (depending on the ambient temperature).