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All Journal Ganendra: Majalah IPTEK Nuklir Mesin
Muhadi Ayub Wasitho
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Computer Science & IT Mechanical Engineering Other

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STUDI EKSPERIMENTAL PROSES QUENCHING BERKAS PIPA PANAS SEBAGAI PEMODELAN PROSES REFLOODING TERAS REAKTOR NUKLIR Wasitho, Muhadi Ayub; Suwono, Aryadi
Mesin Vol 12, No 1 (1997)
Publisher : Mesin

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Abstract

To simulate the thermohydraulic characteristics of reflooding process of a nuclear core reactor during lost of cooling accident, an experimental study using a reduced model was carried-out. The core reactor model consists of a 50 mm tubular transparent shell made of quartz and a bundle of 4 zircaloy-4 pipes of equal diameter 10.7 mm which are equipped with electrical heaters in the inside. The configuration of pipe bundle is in-line with the distance between pipe axis is 14.2 mm. The pipes are identic to those usually used as nuclear reactor fuel claddings. The quenching process was done by flooding the pipe bundle from the bottom. The observation temperature drop of the pipes surface and temperature rise of cooling water for various wetting velocity, initial pipe temperature and cooling water were recorded and analyzed. The quenching phenomenon was also observed visually. The initial pipe temperature and wetting velocity range are 100 - 500 "C and 4 - 20 cm/s, respectively.
STUDI EKSPERIMENTAL PROSES QUENCHING BERKAS PIPA PANAS SEBAGAI PEMODELAN PROSES REFLOODING TERAS REAKTOR NUKLIR Muhadi Ayub Wasitho; Aryadi Suwono
Mesin Vol. 12 No. 1 (1997)
Publisher : Mesin

Show Abstract | Download Original | Original Source | Check in Google Scholar

Abstract

To simulate the thermohydraulic characteristics of reflooding process of a nuclear core reactor during lost of cooling accident, an experimental study using a reduced model was carried-out. The core reactor model consists of a 50 mm tubular transparent shell made of quartz and a bundle of 4 zircaloy-4 pipes of equal diameter 10.7 mm which are equipped with electrical heaters in the inside. The configuration of pipe bundle is in-line with the distance between pipe axis is 14.2 mm. The pipes are identic to those usually used as nuclear reactor fuel claddings. The quenching process was done by flooding the pipe bundle from the bottom. The observation temperature drop of the pipes surface and temperature rise of cooling water for various wetting velocity, initial pipe temperature and cooling water were recorded and analyzed. The quenching phenomenon was also observed visually. The initial pipe temperature and wetting velocity range are 100 - 500 "C and 4 - 20 cm/s, respectively.
Co-Authors Aryadi Suwono Aryadi Suwono Dhandang Purwadi Liliek Harmianto Sudibyo Sudibyo Sukarsono Sukarsono