Study on lead-cooled fast reactor design
Quek, Ernest Tze Yeor
Date of Issue2015
School of Electrical and Electronic Engineering
The demand for new and advance nuclear systems are widely studied all over the world. By the late 2002, under the Generation IV International Forum (GIF) which is an international collective represented by thirteen countries, an international task force was tasked with the research and development of the six nuclear reactor technologies for the future. One of the six Generation IV nuclear reactor is the Lead cooled Fast Reactor. This paper provide an overview of the design features for Lead Fast Reactor (LFR) which will cover two pool-type reactor concepts. One of them is the Small Secure Transportable Autonomous Reactor (SSTAR) while the other is the European Lead-cooled System (ELSY). One of the utmost essential features of LFR is the liquid lead which acts as a coolant for the reactor. With this unique element being used in the system, it allows a greater advantage which coincides to the GIF main focus which is in economics, sustainability, safety, reliability and proliferation-resistance. Pure lead has a high boiling point of 1745 which give a favorable advantage to the security of the system. On the contrary, its melting point of 327.4 is considered to be too high which requires new innovative methods to counter the coolant from freezing and blockage of the circulation throughout the core. At high temperatures, it is necessary to control its purity carefully as it is relatively corrosive towards structural materials. Being used in harsh environment coupled with high energy neutrons effects, it is advisable to make a right choice of material. The main designed features of the ELSY and SSTAR system will be investigated and summarized. Also the key design challenge issues of each system will be presented.
Final Year Project (FYP)
Nanyang Technological University