Introduction of leak-testing method and system for cans of rod-type fuel elements of reactor of first block at the Beloyarsk Atomic Power Plant

1978 ◽  
Vol 45 (3) ◽  
pp. 891-891
Author(s):  
S. V. Shirokov ◽  
�. I. Snitko ◽  
V. N. Shiryaev
Keyword(s):  
Power Plant ◽  
Atomic Power Plant ◽  
Testing Method ◽  
Leak Testing ◽  
Fuel Elements ◽  
Type Fuel

Direct-flow scheme of reactor with smooth tubular fuel elements for maneuverable atomic power plant

1980 ◽  
Vol 48 (1) ◽  
pp. 8-12
Author(s):  
V. N. Smolin ◽  
V. I. Esikov ◽  
Yu. I. Mityaev ◽  
S. A. Vasil'ev
Keyword(s):  
Power Plant ◽  
Atomic Power Plant ◽  
Direct Flow ◽  
Flow Scheme ◽  
Tubular Fuel ◽  
Fuel Elements

Selection Considerations for your Optimum Leak Testing Method and Process

2017 ◽  
Vol 29 (5) ◽  
pp. 18-21 ◽  
Author(s):  
Dave Morris ◽  
Dennis Seibert
Keyword(s):  
Testing Method ◽  
Leak Testing

scholarly journals Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests

1993 ◽  
Vol 204 ◽  
pp. 194-202 ◽  
Author(s):  
Y.Y. Liu ◽  
H. Tsai ◽  
M.C. Billone ◽  
J.W. Holland ◽  
J.M. Kramer
Keyword(s):  
Fuel Elements ◽  
Type Fuel

scholarly journals Studies on Production Planning of Dispersion Type U<sub>3</sub>Si<sub>2</sub>-Al Fuel in Plate-Type Fuel Elements for Nuclear Research Reactors

2016 ◽  
Vol 06 (04) ◽  
pp. 217-231
Author(s):  
Miguel Luiz Miotto Negro ◽  
Michelangelo Durazzo ◽  
Marco Aurélio de Mesquita ◽  
Elita Fontenele Urano de Carvalho ◽  
Delvonei Alves de Andrade
Keyword(s):  
Production Planning ◽  
Nuclear Research ◽  
Research Reactors ◽  
Fuel Elements ◽  
Type Fuel ◽  
Plate Type

scholarly journals Study on Flow Boiling Characteristics in Rectangle Channel After Formation of Blisters

2021 ◽  
Vol 9 ◽  
Author(s):  
Huijian Huang ◽  
Chong Chen ◽  
Luguo Liu ◽  
Yu Liu ◽  
Linfeng Li ◽  
...  
Keyword(s):  
Flow Boiling ◽  
The Novel ◽  
Local Flow ◽  
Flow Through ◽  
Cfd Method ◽  
Dry Out ◽  
Fuel Elements ◽  
Type Fuel ◽  
Plate Type ◽  
Structure Choice

Plate-type fuel elements is one of the first fuel structure choice for the novel integrated PWR, however, blisters will appear on the cladding induced by irradiation and fission. In this work CFD method was used to investigate the subcooled boiling characteristic of the water in rectangle channel with round and pillow blisters, the modified RPI model was also proposed, we can draw conclusions as follows: In the channel with round blister, as the blisters will increase the local flow resistance and more fluid will flow through center of the channel. Boiling occurred only in the area near the edges, nearly no vapor appeared at the center of the channel. The boiling region in channel with pillow shape blisters is wider and concentrated between two pillow blisters and downstream of the non-blisters side. The dry out area are both in the downstream region of blisters for the two types of channels.

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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