OPTIMASI DESAIN TERMOHIDROLIKA TERAS DAN SISTEM PENDINGIN REAKTOR RISET INOVATIF DAYA TINGGI

Authors

  • Endiah Puji Hastuti Pusat Teknologi dan Keselamatan Reaktor Nuklir, BATAN
  • Muhammad Subekti Pusat Teknologi dan Keselamatan Reaktor Nuklir, BATAN
  • Sukmanto Dibyo Pusat Teknologi dan Keselamatan Reaktor Nuklir, BATAN
  • Muhammad Darwis Isnaini Pusat Teknologi dan Keselamatan Reaktor Nuklir, BATAN

DOI:

https://doi.org/10.17146/tdm.2015.17.3.2327

Keywords:

inovative research reactor, Caudvap, PARET-ANL, Fluent, ChemCad 6.4.1

Abstract

THERMALHYDRAULIC DESIGN AND COOLING SYSTEM OPTIMIZATION OF THE HIGH POWER INOVATIVE RESEARCH REACTOR. Reactor innovation has been implemented in a variety of new research reactors that currently are being built. At this time BATAN is designing a conceptual design of the high power research reactor which has entered the stage of design optimization. The conceptual design specifications of the innovative research reactor is a pool type reactor, water-cooled and reflected by D2O. The reactor core has a 5 x 5 grid with 16 fuels and 4 control rods, which is inserted into a tube containing D2O as an irradiation position. Reactor power of 50 MW is designed to generate thermal neutron flux of 5x1014 n/cm2s. The compact core reactor is using U9Mo-Al fuel with uranium loading of 7-9 gU/cm3. Thermal hydraulic design includes modeling, calculation and analysis of the adequacy of coolant created synergy with the physical design of reactor safety. This paper aims to deliver the results of thermal hydraulic calculation and system design analysis at steady state condition. The analysis was done using various calculation programs that have been validated, i.e. Caudvap, PARET-ANL, Fluent and ChemCad 6.4.1. The calculation results show that the heat generation can be transfered without causing a two phase flow boiling by applying pressurized reactor core design, while the main components of initial design system with an integrated heat dissipation has been done, to complete the conceptual design of the RRI-50 thermalhydraulics.

 

References

Endiah Puji Hastuti dkk. BFTR-PTKRN, "User Criteria Document (UCD) Reaktor Riset Inovatif", BATAN-RKN-06-2010.

Saha P., Aksan N., Andersen J., Yan J., Simoneau J.P., LeungL., Bertrand F.,AotogK., KamidegH., Issues and future direction of thermal-hydraulics research and development in nuclear power reactors, Nuclear Engineering and Design 2013; 264:3-23.

https://doi.org/10.1016/j.nucengdes.2012.07.023

Daeseong Jo, Jonghark Park, Heetaek Chae, Development of thermal hydraulic and margin analysis code for steady state forced and natural convective cooling of plate type fuel research reactors, Progress in Nuclear Energy 2014;71:39-51.

https://doi.org/10.1016/j.pnucene.2013.11.006

Qing Lu, Suizheng Qiu, SuG.H., Development of a thermal-hydraulic analysis code for research reactors with plate fuels, Annals of Nuclear Energy 2009;36:433-447.Ramin

https://doi.org/10.1016/j.anucene.2008.11.038

Barati, Saeed Setayeshi, Functional reliability evaluation of an MTR-pool type research reactor core using the load-capacity interference model, Annals of Nuclear Energy2013; 58:151-160.

https://doi.org/10.1016/j.anucene.2013.03.015

Kazem Ardaneh, Salman Zaferanlouei, A lumped parameter core dynamics model for MTR type research reactors under natural convection regime, Annals of Nuclear Energy 2013;56: 243-250.

https://doi.org/10.1016/j.anucene.2013.01.033

Abhinav Dixita, Takashi Hibikia, Mamoru Ishii, Kouichi Tanimoto, Yoshiyuki Kondoh, Koki Hibi, Experimental stability maps for a two-phase natural circulation reactor with and without void-reactivity feedback effect, Nuclear Engineering and Design 2013; 261:181- 200.

https://doi.org/10.1016/j.nucengdes.2013.03.037

Jian Maa, Longjian Li, Yanping Huang, Xiaozhong Liu, Experimental studies on single phase flow and heat transfer in a narrowrectangular channel, Nuclear Engineering and Design 2011;241:2865- 2873.

https://doi.org/10.1016/j.nucengdes.2011.04.047

Jian Zhang, Xiuzhong Shen, Yasuyuki Fujihara, Tadafumi Sano, Toshihiro Yamamoto, Ken Nakajima, Experimental study on the safety of Kyoto University Research Reactor at natural circulation cooling mode, Annals of Nuclear Energy 2015;76:410-420.

https://doi.org/10.1016/j.anucene.2014.10.010

Surip Widodo dkk. BFTR-PTKRN, "Desain Konseptual Reaktor Riset Inovatif", Ident. No. 1/CD01/TRRI/2013.

Sukmanto Dibyo,Endiah Puji Hastuti, Ign. Djoko Irianto, Analisis desain sistem pendingin dan unit komponen pada reaktor RRI-50, Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 2015; 17:19-30.

https://doi.org/10.17146/tdm.2015.17.1.2235

Downloads

Published

2015-12-18

How to Cite

Hastuti, E. P., Subekti, M., Dibyo, S., & Isnaini, M. D. (2015). OPTIMASI DESAIN TERMOHIDROLIKA TERAS DAN SISTEM PENDINGIN REAKTOR RISET INOVATIF DAYA TINGGI. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 17(3), 127–140. https://doi.org/10.17146/tdm.2015.17.3.2327