scholarly journals INSPECTION OF FUEL ELEMENT COMPONENTS AND FUEL ELEMENTS FOR THE ARGONNE LOW POWER REACTOR

1959 ◽  
Author(s):  
W.J. McGonnagle ◽  
W.N. Beck ◽  
N. Lapinski
Keyword(s):  
Fuel Element ◽  
Low Power ◽  
Power Reactor ◽  
Fuel Elements

Studying the Effect of Fuel Elements Structural Materials Corrosion on their Operating Life

2021 ◽  
Vol 1038 ◽  
pp. 108-115
Author(s):  
Yuliana Hapon ◽  
Maksym Kustov ◽  
Volodumur Kalugin ◽  
Alexander Savchenko
Keyword(s):  
Experimental Data ◽  
Mass Transfer ◽  
Fuel Element ◽  
State Level ◽  
External Factors ◽  
Economic Losses ◽  
Operating Life ◽  
Hydrodynamic Mode ◽  
Internal And External Factors ◽  
Fuel Elements

The paper deals with experimental data regarding the effect of internal and external factors on the corrosion decay of Zr1Nb alloy fuel elements. Based on the analysis results, losses of zirconium that transfers to oxide or coolant as per the fuel element wall weight and thickness as well as economic losses from their corrosion decay have been theoretically calculated. To avoid a state-level emergency occurrence, an increase in the fuel element wall thickness up to 660 μm is proposed, which can increase the operating life under the conditions of trouble-free coolant mass transfer hydrodynamic mode.

Study on Temperature Distribution of Pebble-Bed HTR Fuel Element by Using Boundary Element Method

2013 ◽  
Author(s):  
Haitao Wang ◽  
Xin Wang
Keyword(s):  
Fuel Element ◽  
Boundary Element ◽  
Large Scale ◽  
Maximum Temperature ◽  
Element Formulation ◽  
Desktop Computer ◽  
Pebble Bed ◽  
Graphite Matrix ◽  
Fuel Particles ◽  
Fuel Elements

Spherical fuel elements with a diameter of 60mm are basic units of the nuclear fuel for the pebble-bed high temperature gas-cooled reactor (HTR). Each fuel element is treated as a graphite matrix containing around 10,000 randomly distributed fuel particles. The essential safety concept of the pebble-bed HTR is based on the objective that maximum temperature of the fuel particles does not exceed the design value. In this paper, a microstructure-based boundary element model is proposed for the large-scale thermal analysis of a spherical fuel element. This model presents detailed structural information of a large number of coated fuel particles dispersed in a spherical graphite matrix in order that temperature distributions at the level of fuel particles can be evaluated. The model is meshed with boundary elements in conjunction with the fast multipole method (FMM) in order that such large-scale computation is performed only in a personal desktop computer. Taking advantage of the fact that fuel particles are of the same shape, a similar sub-domain approach is used to establish the temperature translation mechanism between various layers of each fuel particle and to simplify the associated boundary element formulation. The numerical results demonstrate large-scale capacity of the proposed method for the multi-level temperature evaluation of the pebble-bed HTR fuel elements.

scholarly journals Implementation of the partial dismantling of research reactor IRT-Sofia prior to its refurbishment

2010 ◽  
Vol 25 (3) ◽  
pp. 249-254 ◽  
Author(s):  
Tihomir Apostolov ◽  
Elka Anastasova ◽  
Valentin Anastassov
Keyword(s):  
Low Power ◽  
Research Reactor ◽  
Power Reactor ◽  
Engineering Project ◽  
Available Resources

In 2001, the Bulgarian Government decided to refurbish and convert the research reactor in Sofia into a low-power reactor. Due to this, a partial dismantling of IRT-Sofia?s old systems and equipment was carried out with the intention of reusing the concrete bioshield in the construction of the new low-power research reactor. For a more efficient use of available resources, an engineering project known as ?The plan for the partial dismantling of IRT-Sofia equipment as a part of its refurbishment into a low-power research reactor? was drawn up and has since been successfully implemented.

scholarly journals ALPR PRELIMINARY DESIGN STUDY (ARGONNE LOW POWER REACTOR). PHASE I

1956 ◽  
Author(s):  
M. Treshow ◽  
E. Hamer ◽  
H. Pearlman ◽  
D. Rossin ◽  
D. Shaftman
Keyword(s):  
Low Power ◽  
Phase I ◽  
Power Reactor ◽  
Preliminary Design ◽  
Design Study

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 Thorium-loaded low-power reactor installation operated with super-long fuel residence time

2016 ◽  
Vol 2 (3) ◽  
pp. 172-178
Author(s):  
I.V. Shamanin ◽  
S.V. Bedenko ◽  
Yu.B. Chertkov
Keyword(s):  
Low Power ◽  
Residence Time ◽  
Power Reactor ◽  
Reactor Installation

Risk reduction design alternatives for low-power and shutdown operation of a 1500-MW advanced power reactor with a passive auxiliary feedwater system

2020 ◽  
Vol 129 ◽  
pp. 103492
Author(s):  
Ho Rim Moon ◽  
Deok Sung Han ◽  
Jae Gab Kim ◽  
Ji Yong Oh ◽  
Sang Won Lee ◽  
...  
Keyword(s):  
Low Power ◽  
Risk Reduction ◽  
Power Reactor ◽  
Design Alternatives
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