ANALISIS TERMOHIDRAULIKA TARGET LEU PENGHASIL FPM DENGAN PROGRAM COBRA IV-I

ABSTRAK
ANALISIS TERMOHIDROLIKA TARGET LEU PENGHASIL FPM DENGAN PROGRAM COBRA IVI.
Telah dilakukan analisis termohidraulika untuk iradiasi target LEU (Low Enriched Uranium)
penghasil FPM ( Fission Product Molybdenum) di dalam teras reaktor. Batas keselamatan (Safety
Margin) yang digunakan adalah Minimum Departure from Nucleat Boiling Ratio (MDNBR). Analisis
dilakukan dengan menggunakan paket program komputer COBRA IV-I yang dikembangkan oleh The
Pacific Northwest Laboratory, Battele Northwest. Data masukan laju alir pendingin dan fluks neutron
diperoleh dari pengukuran. Perhitungan dilakukan dengan berbagai variasi massa U235. Untuk
muatan U235 sebesar 6 gr diperoleh laju pembangkitan panas dari fisi dan gamma heating sebesar
26,11 kW, sedangkan dari hasil perhitungan diperoleh temperatur kelongsong 163,06 °c, temperatur
pending in 47,06 °c, koefisien perpindahan panas 33,611 kW/(m2K) dan MDNBR sebesar 1,62.
ABSTRACT
THERMAL -/:IYDRAULICS ANALYSIS OF LEU TARGETS PRODUCING FPM USING
COBRA IV-I. Thermal-hydraulics analysis of the L~EU (Low Enriched Uranium) producing FPM
(Fission Product Molybdenum) targets irradiated in the reactor core of RSG-GAS have been done. A
safety margin applied was based on the Minimum Departure from Nucleat Boiling Ratio. The analysis
was done using COBRA IV-I developed in the Pacific Northwest Laboratory. The input data for the
coolant flow rates and neutron flux were based on the measurement results. The calculations were
done for different weight mass of LEU targets. The heat generated in 6-gr U235 LEU target from
fission and gamma heating is 26.11 kW. The .calculation results showed that the cladding
temperature, coolant temperature, heat transfer coeficient along the targets, and MDNBR were
163.06 DC, 47.06 DC, 33.611 kW/(m2.K) and 1.62 respectively.