Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR) can produce steam from the
direct contact of feed-water and lead bismuth eutectic (LBE) in the chimney of 3 m height …

The prospect of uranium nitride (UN-PuN) fuel for 25-100MWe Gas Cooled Fast Reactor has
been done. This research use helium coolant which has low neutron moderation, chemical …

This paper reports a conceptual design study of Pb-Bi cooled fast reactors with a fuel cycle
that needs only natural uranium input. In this design, the CANDLE burn-up strategy is …

The neutronic analysis of full-core 3-dimensional geometrical modeling for a CANDLE
reactor was conducted in this study, utilizing uranium nitride fuel and the MCNP6 code …

Design study of Pb-Bi cooled fast reactors with natural uranium as fuel cycle input using
special radial shuffling strategy has been performed. The reactors utilizes UN-PUN as fuel …

Salah satu aspek terpenting dalam proses desain reaktor nuklir adalah aspek keselamatan
reaktor. Sebelum membangun reaktor secara fisik, terlebih dahulu dibuat perencaaan …

Design study of gas cooled fast reactors with natural uranium as fuel cycle input has been
performed. The reactors utilizes UN-PUN as fuel, helium as coolant, and can be operated …

This paper discusses the development of program code that coupling the ORIGEN2. 2 for
burn-up analysis with the Monte Carlo program OpenMC for neutron analysis program …

In this study application of modified CANDLE burn-up scheme for medium-sized (800–1500
MWt) long-life Pb-Bi cooled fast reactors with natural uranium as fuel cycle input has been …

Zero burn-up core capability can eliminate possible super prompt critical accident and make
possible of inherent safety feature based on reactivity feedback mechanism. In this concept …