Evaluation and Analysis of Cooling Study of High Temperature Heated Rod on Queen-II Test Section for Bottom Reflooding Procces experiments

EVALUATION AND ANALYSIS OF COOLING STUDY OF HIGH TEMPERATURE HEATED ROD ON QUEEN-II TEST SECTION FOR BOTTOM REFLOODING PROCESS EXPERIMENTS.

Puradwi I.W., M. Juarsa, Hendro Tj.
Pusat Teknologi Reaktor dan Keselamatan Nuklir - BATAN
Kawasan PUSPIPTEK Gedung 80, Serpong 15310, Tangerang
ABSTRACT
EVALUATION AND ANALYSIS OF COOLING STUDY OF HIGH TEMPERATURE HEATED ROD ON QUEEN-II TEST SECTION FOR BOTTOM REFLOODING PROCESS EXPERIMENTS. Emergency cooling processes of LOCA in PWR is done by core reflooding especially to cooling fuel rod which is still hot, with bottom reflooding of water flow is injected from ECCS to reactor core. The bottom reflooding phenomenon is necessary to investigated and to understood through post LOCA boiling heat transfer phenomenons on fuel rod with boiling heat transfer experiments and the end results are heat flux and boiling curves. The Experimental simulation of heated rod which is cooled from bottom to up by water cooling flow, was done using water cooling flow rate variation G= 15 g/s, G= 59 g/s dan G= 140 g/s at 850-900 oC of temperature and initial heated rod temperature variation as 600 oC, 700 oC and 800 oC on 62 g/s flow rate. Analysis was done base on the measurement, visualization, and analytic calculations. The experiment results was showing that the heat transfer on bottom reflooding is occurred an film boiling heat transfer at bottom reflooding process which is initiating the cooling process of the bottom reflooding mainly on initial heated rod temperature higher than 800 oC. For initial heated rod temperature variations with same flow rate, MHF and CHF values are tend to increase for higher initial heated rod temperature. The evaluation of study results was saw that boiling curve is resulted through transient cooling of the high temperature heated rod and the boiling is a flow boiling. This flow boiling was saw that post burn out film boiling and flow rate variable and initial heated rod temperature were give important meaning in the cooling process of post LOCA mainly on MHF and CHF.

Keywords: boiling, film, heat transfer, bottom reflooding, LOCA.
Prosiding Seminar Nasional Ke-15 "TEKNOLOGI DAN KESELAMATAN PLTN SERTA FASILITAS NUKLIR", Surakarta, 17 Oktober 2009

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The Probabilistic Analysis Of Power Reactor Radiation Safety At LOCA (Loss Of Coolant Accident) Condition

THE PROBABILISTIC ANALYSIS OF POWER REACTOR RADIATION SAFETY AT LOCA (LOSS OF COOLANT ACCIDENT) CONDITION

Pande Made Udiyani
Pusat Teknologi Reaktor dan Keselamatan Nuklir - BATAN
PTRKN-BATAN, Kawasan PUSPIPTEK Gd.80, Serpong, Tangerang, 15310
ABSTRACT
THE PROBABILISTIC ANALYSIS OF POWER REACTOR RADIATION SAFETY AT LOCA (LOSS OF COOLANT ACCIDENT) CONDITION. Operation of power reactor NPPs (Nuclear Power Plants) requires important document safety analysis. The objectives this paper is to get supporting data for Safety Analysis Report (SAR) document. The probabilistic analysis for radiologic and environment consequences done at accident condition with LOCA postulation. The assumption of LOCA is Large Break Loss of Coolant Accident ) based on the fourth level of DBA (Design Basis Accident),which was started double guillotine break in the primary pipes. The assumptions of fission product releases from core inventory to containment are: Emergency core cooling system (ECCS) injection cold and hot legs types, 3 % failed fuel fraction; by gap inventory; fraction of the core inventory present in the gap are: 7,5 % Kr; noble gas Xe 3,95 %; and Iodine is 0,65 %. Released core inventory to containment for Kr-85 is 0,23%, Xe-133 (0,07 %), I-131 (0,02 %) and Cs-137 (0,06 %). The containment is without spray system. Source term data are from PWR 1000 MWe generic power reactor with Muria Peninshula site study. The radiology consequences was estimated by PC Cosyma programme code with probabilistic calculating mode. From various pathway, the estimation results are: the maximum mean individual probability distributions dose is 2,98 x 10-4 mSv/year for 1 km radius reactor distances. This dose is under BAPETEN and IAEA dose limit for accident.

Key words: probabilistic, radiation dose, LOCA, safety
Published : Proceeding "SEMINAR NASIONAL PENGEMBANGAN ENERGI NUKLIR II 2009", Jakarta, 25 Juni 2009

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