Abstract
Design study of 200 MWth Gas Cooled Fast Reactor with UN-PuN fuel long life without refueling has been done. GFR is one type reactor in Generation IV reactor system. It uses helium coolant and fast neutron spectrum. Helium is chemical inert, single phase and low neutron moderation. In this study the calculations are performed by using SRAC code with PIJ calculation for the fuel pin cell calculation and CITATION calculation for core calculation. The data libraries use JENDL 3.2. The variation fuel fractions are 50% until 60%. The diameter active core is 150 cm and the height active core is 100 cm. The reflector radial-axial width is 50 cm. The variation of the powers are 100 MWth up to 500 MWth. The high power causes the high k-eff value. The optimum design is reached when the power is 200 MWth, variation percentage Plutonium for fuel F1:F2:F3=9%:11%:13%. The comparation of fuel:cladding:coolant fraction = 55%:10%:35%. The cooling down time of Plutonium is nine months. The optimum k-eff value is 1.0142 with excess reactivity value 1.403%. The decay of Plutonium decrease k-eff value in the beginning of burn up.
Highlights
Nuclear power plants, which produce low-carbon electricity at stable and competitive costs, constitute an element of the solution to global warming and means of delivering power to emerging and developed countries
The Fukushima Daiichi nuclear power plant accident has emphasized the important of designing nuclear systems with highest levels of safety
Lessons learnt from the accident will benefit the current operating fleet, as well as future nuclear system, including Generation IV systems [1]
Summary
Nuclear power plants, which produce low-carbon electricity at stable and competitive costs, constitute an element of the solution to global warming and means of delivering power to emerging and developed countries. Further development of nuclear technology is needed to meet future energy demand [1]. Lessons learnt from the accident will benefit the current operating fleet, as well as future nuclear system, including Generation IV systems [1]. Challenging technology goals for Generation IV nuclear energy system are defined in four areas. They are sustainability, economics, safety and reliability, and proliferation resistance and physical protection. There are six systems of Generation IV technologies, i.e. Gas Cooled Fast Reactor (GFR), Lead Cooled Fast Reactor (LFR), Molten Salt Reactor (MSR), Sodium Cooled Fast Reactor (SFR), Supercritical Water Cooled Reactor (SCWR), and Very High Temperature Reactor (VHTR) [2]. In this research design study of 200 MWth GFR with nitride fuel long life without refueling has been done
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