PERHITUNGAN FLUKS KALOR UNTUK KURVA DIDIH SELAMA EKSPERIMEN QUENCHINGMENGGUNAKAN SILINDER BERONGGA DIPANASKAN

Authors

  • Mulya Juarsa Departemen Teknik Mesin, Fakultas Teknik, University of Indonesia
  • Raldi Artono Koestor Departemen Teknik Mesin, Fakultas Teknik, University of Indonesia
  • Nandy Setiadi Djaya Putra Departemen Teknik Mesin, Fakultas Teknik, University of Indonesia
  • Anhar Riza Antariksawan Badan Tenaga Nuklir Nasional (BATAN)
  • Cukup Mulyana KBK Fisika Energi, Jurusan Fisika FMIPA, Universitas Padjadjaran
  • Riska Khalisa KBK Fisika Energi, Jurusan Fisika FMIPA, Universitas Padjadjaran

Keywords:

quenching, cylinder, boiling, heat flux

Abstract

One of the safety management aspects in the operation of nuclear reactors is thermal management. The basic concept of thermal management is to control the excess heat during an accident. The understanding and investigation of boiling phenomenon become important research stage. Quenching process is the process of sudden cooling on a hot object by entering into a fluid. SS316 material with hollow cylinder geometry in a vertical position is the simulation of debris and used as a heated object. Method of quenching experiments carried out through the natural cooling of the hollow cylinder with different variations of initial temperature from 300 oC to 800 oC and submerged into the water with saturation temperature. Temperature data was recorded and boiling was captured using highspeed camera (HSC) during the experiment. The results of transient temperature data was used to calculate the heat flux. The film boiling regime on TC8 (outer portion) in the boiling curves for all initial temperatures have a good agreement with Bromley’s correlation. The shortest process of film boiling was occurred for 1.11 seconds at the initial temperature of 300oC. Critical heat flux at TC8 from initial temperature of 800 oC, 600 oC, 400 oC and 300 oC in respectively is 700 kW/m2, 500 kW/m2, 450 kW/m2 and 400 kW/m2.

 

 

References

Broughton JM, Kuan P, Petti DA and Tolma EL. A Scenario on the three mile island unit 2 accident. Nuclear Technology. 2005;87(1):34-5.

https://doi.org/10.13182/NT89-A27637

How the safety of npp is secured in policy terms. Hopes to Make Safe More Secured. Serial, NPP Safety Demonstration/Analysis, ANRE & MITI Japan; 2001.

World Nuclear Association. Three Mile Island Accident. [cited 2010 December 25]. Available: http://www.world-nuclear.org/info/inf36.html.

Juarsa M. Simulasi eksperimental kecelakaan parah pada pemahaman aspek manajemen kecelakaa. J Tek Pengolahan Limbah. Juli 2007; 10(1):58-65.

Juarsa M, Umar E, Widiharto A. Analisis fluks kalor pada celah sempit anulus dengan variasi temperatur awal menggunakan bagian uji HeaTiNG-01. BATAN ITB. Bandung, 2009: 72-80.

Juarsa M, Wahono PI, Antariksawan AR. Studi fenomena perpindahan panas pendidihan berdasarkan peristiwa LOCA dan kecelakaan parah. J Nas Sains dan Teknologi Nuklir. Agustus 2009; IX(2);1-15.

Lienhard IV JH. Lienhard V JH. A heat transfer textbook. 3th ed. Cambridge: Phlogiston Press; 2002.

https://doi.org/10.1080/01457630304074

De Witt DP. and Frank P, Incropera FP. Fundamental of heat transfer. John New York: Wiley & Sons, Inc; 1981.

Bejan A. and Kraus AD. Heat transfer hand book. Canada:John Wiley & Sons; 2003.

Bromley LA. Heat transfer in stable film boiling. Chem Eng Progress 1950; 46:221- 32.

Downloads

Published

2015-04-04

How to Cite

Juarsa, M., Koestor, R. A., Putra, N. S. D., Antariksawan, A. R., Mulyana, C., & Khalisa, R. (2015). PERHITUNGAN FLUKS KALOR UNTUK KURVA DIDIH SELAMA EKSPERIMEN QUENCHINGMENGGUNAKAN SILINDER BERONGGA DIPANASKAN. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 12(3), 127–145. Retrieved from https://ejournal.brin.go.id/tridam/article/view/2361