Natural convection cooling characteristics in a plate type fuel assembly of Kyoto University Research Reactor during loss of coolant accident

2016 ◽  
Vol 90 ◽  
pp. 1-8 ◽  
Author(s):  
Daisuke Ito ◽  
Yasushi Saito
Keyword(s):  
Natural Convection ◽  
Fuel Assembly ◽  
Research Reactor ◽  
University Research ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Convection Cooling ◽  
Type Fuel ◽  
Plate Type

scholarly journals DROP IMPACT ANALYSIS OF PLATE-TYPE FUEL ASSEMBLY IN RESEARCH REACTOR

2014 ◽  
Vol 46 (4) ◽  
pp. 529-540 ◽  
Author(s):  
HYUN-JUNG KIM ◽  
JEONG-SIK YIM ◽  
BYUNG-HO LEE ◽  
JAE-YONG OH ◽  
YOUNG-WOOK TAHK
Keyword(s):  
Fuel Assembly ◽  
Impact Analysis ◽  
Research Reactor ◽  
Drop Impact ◽  
Type Fuel ◽  
Plate Type

Measurement of core flow distribution in a research reactor using plate-type fuel assembly

2020 ◽  
Vol 148 ◽  
pp. 107750
Author(s):  
Jonghark Park ◽  
Hyung Min Son ◽  
Kiwon Song ◽  
Ragai M. Altamimi
Keyword(s):  
Fuel Assembly ◽  
Research Reactor ◽  
Flow Distribution ◽  
Core Flow ◽  
Type Fuel ◽  
Plate Type

scholarly journals Numerical Investigation of Conjugated Heat Transfer of the Plate-Type Fuel Assembly in the Research Reactor

2021 ◽  
Vol 9 ◽  
Author(s):  
Quan Li ◽  
Qiang Ma ◽  
Yuanming Li ◽  
Ping Chen ◽  
Chao Ma ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Fuel Assembly ◽  
Power Density ◽  
Research Reactor ◽  
Flow Boiling ◽  
Fluid Velocity ◽  
Rensselaer Polytechnic Institute ◽  
Conjugated Heat Transfer ◽  
Type Fuel ◽  
Plate Type

In nuclear reactors, the research of conjugated heat transfer between the fuel and coolant in the fuel assembly is fundamental for improving the safety, reliability and economy. The numerical approach based on Computational Fluid Dynamics (CFD) can be used to realize the rapid analysis of the conjugated heat transfer. Besides, the numerical simulation can provide detailed physical fields that are useful for the designing and optimizing of the fuel assembly. The plate-type fuels are generally used to enhance heat transfer in research reactors with high power density. In this study, a standard plate-type fuel assembly in the research reactor was taken into consideration. The solid-fluid conjugated heat transfer of the fuel assembly and coolant was numerically investigated. In the fluid region, the subcooled flow boiling simulation model was established by implementing the Rensselaer Polytechnic Institute model into the Euler multi-phase flow method. The results show that the conjugated heat transfer of the fuel assembly and coolant can be simulated using the model established in this work. The influence of fluid velocity, power density and the width of the flow channel on the temperature distribution and the conjugated heat transfer was investigated and discussed.

Drop behaviors of a plate-type fuel assembly used in research reactor for a drop accident

2019 ◽  
Vol 113 ◽  
pp. 255-262
Author(s):  
Hyun-Jung Kim ◽  
Jeong-Sik Yim ◽  
Young-Wook Tahk ◽  
Jae-Yong Oh ◽  
Eui-Hyun Kong
Keyword(s):  
Fuel Assembly ◽  
Research Reactor ◽  
Type Fuel ◽  
Plate Type

scholarly journals THE THERMOHYDRAULIC ANALYSIS OF THE BANDUNG RESEARCH REACTOR CORE WITH PLATE TYPE FUEL ELEMENTS USING THE CFD CODE

2018 ◽  
Vol 20 (3) ◽  
pp. 123
Author(s):  
Reinaldy Nazar ◽  
Sudjatmi KA ◽  
Ketut Kamajaya
Keyword(s):  
Fuel Element ◽  
Surface Temperature ◽  
Forced Convection ◽  
Flow Rate ◽  
Research Reactor ◽  
Saturation Temperature ◽  
Cooling Flow ◽  
Fuel Elements ◽  
Type Fuel ◽  
Plate Type

Due to TRIGA fuel elements are no longer produced by General Atomic, it is necessary to find a solution so that the Bandung TRIGA 2000 reactor can still be operated. One solution is to replace the type of fuel elements. Study on using the MTR plate type fuel elements as used in RSG-GAS Serpong has been done for the Bandung TRIGA 2000. Based on the results of the study using CFD computer program, it is found that Bandung TRIGA 2000 with plate type fuel elements cannot be operated up to 2000 kW power by natural convection cooling mode. Therefore, the reactor must be cooled by forced convection. The analysis using forced convection showed that for cooling flow rate of 50 kg/s and various temperatures of 35oC, 35.5 oC and 36 oC, the surface temperature of the fuel element is between 110.37 oC and 111.27 oC. Meanwhile, the cooling water temperature in the corresponding position is between 61.03 oC and 61.95 oC. In this operation condition, the surface temperatures of fuel elements can approach the saturation temperature and nucleat boiling started to occur. Hence, the use of cooling flow rate entering core less than 50 kg/s should be avoided. The surface temperature of fuel elements decreased under saturation temperature if cooling flow rate is greater than 65 kg/s. The surface temperature of fuel elements is achieved at 96.65 oC and coolant temperature in the corresponding position was 54.38 oC. Keywords: Bandung research reactor, plate type fuel element, thermohydraulic, CFD code ANALISIS TERMOHIDROLIK TERAS REAKTOR RISET BANDUNG BERELEMEN BAKAR TIPE PELAT MENGGUNAKAN PROGRAM CFD. Mengingat tidak diproduksinya lagi elemen bakar TRIGA oleh General Atomic, maka perlu diusahakan suatu solusi agar reaktor TRIGA 2000 Bandung dapat tetap beroperasi. Salah satu solusi adalah dengan melakukan penggantian tipe elemen bakar. Pada studi ini telah dianalisis penggunaan elemen bakar tipe pelat yang sejenis dengan yang digunakan di RSG-GAS Serpong, untuk digunakankan pada teras reaktor TRIGA 2000 Bandung. Berdasarkan hasil penelitian yang telah dilakukan dengan menggunakan program komputer CFD, diketahui bahwa reaktor TRIGA berelemen bakar tipe pelat tidak dapat dioperasikan pada daya 2000 kW dengan menggunakan moda pendinginan konveksi alamiah seperti yang digunakan saat ini. Untuk kondisi ini, pendinginan dilakukan dengan moda pendinginan konveksi paksa. Hasil analisis konveksi paksa menunjukkan bahwa dengan menggunakan laju alir pendingin pompa 50 kg/s dan variasi temperatur pada 35 oC, 35,5 oC dan 36 oC, diperoleh temperatur permukaan pelat elemen bakar antara 110,37 oC – 111,27 oC dan temperatur pendinginnya pada posisi terkait antara 61,03 oC – 61,95 oC. Temperatur permukaan pelat elemen bakar ini mendekati temperatur saturasi dan tentunya telah mulai terjadi pendidihan inti, sehingga penggunaan laju alir pendingin masuk teras reaktor kurang dari 50 kg/s perlu dihindari. Temperatur permukaan pelat elemen bakar mulai menurun menjauhi temperatur saturasi jika digunakan laju alir pendingin lebih besar dari 65 kg/s, dengan temperatur permukaan pelat elemen bakar 96,65 oC dan temperatur pendinginnya pada posisi terkait 54,38 oC.Kata kunci: Reaktor riset Bandung, elemen bakar tipe pelat, termohidrolik, program CFD

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