Seminarium Zakładu Energetyki Jądrowej i Analiz Środowiska

English translation unavailable for Optymalizacja projektu systemu odbioru ciepła powyłączeniowego (DHR) reaktora ALLEGRO w ramach projektu VINCO.
English translation unavailable for Wstępna analiza reaktora dwupłynowego z płynnym paliwem metalicznym.
English translation unavailable for Czy reaktor dwupłynowy (DFR) to Generacja IV czy V?.
English translation unavailable for Reaktory wysokotemperaturowe w Polsce – problemy i wyzwania.
English translation unavailable for Towards the Direct Numerical Simulation of a closely-spaced bare rod bundle.
English translation unavailable for Direct Numerical Simulation of a Simplified Pressurized Thermal Shock.
English translation unavailable for Wypalanie U-238 i Th-232 w reaktorach jądrowych.
English translation unavailable for Nowy zderzacz NICA (Dubna) i polski udział w jego budowie.

HTGR development in Japan

Japan Atomic Energy Agency(JAEA) has developed the High Temperature Engineering Test Reactor (HTTR), the first HTGR in Japan. The reactor power is 30MW and the outlet helium-gas temperature is 950C at the maximum. HTTR uses block type fuel element. In the presentation at the seminar, the outline of the structure of HTTR, development history, safety features will be presented.


Impact of Recent Advancements in Multiphase Science on Nuclear Reactor Thermal-Hydraulics and Safety Studies

The recent progress in multiphase science and technology has made a considerable impact on nuclear reactor thermal-hydraulics.  However, the needs for obtaining solutions to a variety of practical questions have had both pros and cons.   The former have been reflected in the role of needs as an obvious research stimulation factor, the latter have been due to fact that the urgency of producing results often limited systematic investigations of the underlying physics.