ANALISIS TINGKAT SIRKULASI ALAMIAH PADA LIQUID METAL FAST BREEDER REACTOR DENGAN PENDINGIN Na, NaK, Pb DAN Pb-Bi

REFI, JUITA (2019) ANALISIS TINGKAT SIRKULASI ALAMIAH PADA LIQUID METAL FAST BREEDER REACTOR DENGAN PENDINGIN Na, NaK, Pb DAN Pb-Bi. Diploma thesis, Universitas Andalas.

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Abstract

Telah dilakukan analisis tingkat sirkulasi alamiah pada LMFBR (Liquid Metal Fast Breeder Reactor) dengan bahan pendingin Na, NaK, Pb dan Pb-Bi. Perhitungan neutronik dan termalhidrolik pada penelitian ini menggunakan program DTRIDI berbasis delphi7 yang merupakan program simulasi untuk desain teras tiga dimensi (xyz). Teras LMFBR dirancang dengan bahan bakar UN-PuN dan beroperasi pada daya 150 MWth. Simulasi diawali dengan perhitungan neutronik yang memberikan hasil faktor multiplikasi neutron yang digunakan untuk perhitungan termalhidrolik sehingga diperoleh distribusi temperatur dan penurunan tekanan. Analisis tingkat sirkukasi alamiah dilakukan dengan pendekatan kuasistatik, dimana laju aliran massa pendingin total diturunkan secara bertahap untuk mensimulasikan hilangnya daya pompa pada keadaan kecelakaan ULOF (Unprotected Lost Of Flow). Tingkat sirkulasi alamiah diperoleh dari grafik perpotongan antara pressure drop dan driving head sebagai fungsi dari laju alir pendingin total. Sirkulasi alamiah tercapai lebih cepat pada penggunaan bahan pendingin Pb dan Pb-Bi yaitu sekitar 27,5 % dari laju aliran pendingin mula-mula, sedangkan untuk penggunaan pendingin Na dan NaK hampir tidak terjadi sirkulasi alamiah yang berarti reaktor dalam keadaan bahaya jika terjadi kecelakaan ULOF. Kata kunci: sirkulasi alamiah, LMFBR, ULOF, Na, NaK, Pb, Pb-Bi Natural circulation level analysis has been carried out on LMFBR (Liquid Metal Fast Breeder Reactor) with coolant Na, NaK, Pb and Pb-Bi. The neutronic and thermal hydraulics calculations in this study used the delphi7-based DTRIDI program which is a simulation program for three-dimensional core design (xyz). The LMFBR core is designed with UN-PuN fuel and operates at 150 MWth. The simulation begins with a neutron calculation which results in a neutron multiplication factor used for thermal hydraulic calculations so that the temperature distribution and pressure drop are obtained. Natural circulation level analysis is carried out by the quasi-static approach, where the total coolant mass flow rate is gradually reduced to simulate the loss of pump power at the ULOF (Unprotected Lost Of Flow) accident. The natural circulation level is obtained from graphic interception between the pressure drop and driving head as a function of total coolant mass flow rate. Natural circulation is achieved more quickly in the use of Pb and Pb-Bi coolant, which is about 27.5% of the initial coolant flow rate, whereas for the use of coolant Na and NaK there is almost no natural circulation which means the reactor is in danger of ULOF accident due to loss of pump power. Keyword: natural circulation, LMFBR, ULOF, Na, NaK, Pb, Pb-Bi

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