scholarly journals SPECIFICATIONS AND PROCEDURES USED IN MANUFACTURING U$sub 3$O$sub 8$- ALUMINUM DISPERSION FUEL ELEMENTS FOR CORE I OF THE PUERTO RICO RESEARCH REACTOR

1963 ◽  
Author(s):  
W.J. Kucera ◽  
C.F. Jr. Leitten ◽  
R.J. Beaver
Keyword(s):  
Puerto Rico ◽  
Research Reactor ◽  
Dispersion Fuel ◽  
Fuel Elements

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

scholarly journals DEVELOPMENT OF URANIUM NITRIDE-STAINLESS STEEL DISPERSION FUEL ELEMENTS

1959 ◽  
Author(s):  
S.J. Paprocki ◽  
D.L. Keller ◽  
G.W. Cunningham ◽  
A.K. Jr. Foulds
Keyword(s):  
Stainless Steel ◽  
Dispersion Fuel ◽  
Uranium Nitride ◽  
Fuel Elements

scholarly journals Design and fabrication of the instrumented fuel elements for the Annular Core Research Reactor (ACRR)

1981 ◽  
Author(s):  
T Schmidt ◽  
D Sasmor ◽  
J Martin ◽  
F Gonzalez ◽  
D Cox
Keyword(s):  
Research Reactor ◽  
Fuel Elements

Measurement of the Volume, Pressure, and Composition of Gases Inside a Bulge in Irradiated Fuel Elements with Uranium-Molybdenum Dispersion Fuel

Atomic Energy ◽  
2017 ◽  
Vol 121 (4) ◽  
pp. 265-268
Author(s):  
O. A. Golosov ◽  
V. N. Nikolkin ◽  
M. S. Lyutikova ◽  
V. V. Bedin ◽  
A. A. D’yakov
Keyword(s):  
Dispersion Fuel ◽  
Fuel Elements ◽  
Irradiated Fuel

Design of U3Si2-Al Plate-Type Fuel Element for China Advanced Research Reactor

2010 ◽  
Author(s):  
Aimin Zhang ◽  
Yalun Kang
Keyword(s):  
Fuel Element ◽  
Neutron Flux ◽  
Research Reactor ◽  
High Heat ◽  
Reactor Power ◽  
High Heat Flux ◽  
Water Tank ◽  
Enriched Uranium ◽  
Fuel Elements ◽  
Plate Type

China Advanced Research Reactor (CARR), which will be critical in China Institute of Atomic Energy (CIAE) in 2010, is a multipurpose, high neutron flux and tank-type (inverse neutron trap) reactor with compact core. Its nominal reactor power is 60MW and the maximum thermal neutron flux is about 8.0×1014n/cm2·s in heavy water tank. It has a cylindrical core having a diameter of about 450mm and a height of 850mm. The CARR’s core consists of seventeen plate-type standard fuel elements and four follower fuel elements, initially loaded with 10.97 kg of 235U. The fuel element has been designed with U3S2-Al dispersion containing 235U of (19.75±0.20)wt.% low enriched uranium (LEU) and having a density of 4.3gU/cm3. The aluminum alloy is used as the cladding. There are twenty-one and seventeen fuel plates in the standard and follower fuel element, respectively. There are specific requirements for design of the fuel element and strict limitation for the operation parameters due to the high heat flux and high velocity of coolant in CARR. Irradiation test of fuel element had been carried out at fuel element power of 3.1±20%MW at Russia MIR reactor. Average burnup of fuel element is up to 40%. This paper deals with the detailed design of fuel element for CARR, out-pile and in-pile test projects, including selection of fuel and structure material, description of element structure, miniplates and fuel element irradiation experiment, measurement of properties of fuel plate, fabrication of fuel element and test results.

Swelling of Uranium Dioxide–Silumin Dispersion Fuel Composition in Experimental Fuel Elements of the SM Reactor

Atomic Energy ◽  
2018 ◽  
Vol 124 (1) ◽  
pp. 28-35
Author(s):  
I. F. Gil’mutdinov ◽  
V. Yu. Shishin ◽  
F. N. Kryukov ◽  
S. V. Kuz’min ◽  
P. P. Silant’ev ◽  
...  
Keyword(s):  
Uranium Dioxide ◽  
Fuel Composition ◽  
Dispersion Fuel ◽  
Fuel Elements

Irradiation behavior of low-enriched U6Fe-Ai dispersion fuel elements

1987 ◽  
Vol 150 (2) ◽  
pp. 238-243 ◽  
Author(s):  
G.L. Hofman ◽  
R.F. Domagala ◽  
G.L. Copeland
Keyword(s):  
Dispersion Fuel ◽  
Fuel Elements ◽  
Irradiation Behavior
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