U3Si2-SiC fuel performance analysis in BISON during normal operation

2019 ◽  
Vol 132 ◽  
pp. 34-45 ◽  
Author(s):  
Wei Li ◽  
Koroush Shirvan
Keyword(s):  
Performance Analysis ◽  
Normal Operation ◽  
Fuel Performance

Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software

2020 ◽  
Author(s):  
Changbing Tang ◽  
Yongjun Jiao ◽  
Yuanming Li ◽  
Yi Zhou ◽  
Kun Zhang
Keyword(s):  
Performance Analysis ◽  
Contact Pressure ◽  
Nuclear Fuel ◽  
Local Stress ◽  
Simulation Method ◽  
Operating Conditions ◽  
Effective Control ◽  
Mechanical Interaction ◽  
Fuel Performance ◽  
Abaqus Software

Abstract The cladding acts as the first barrier to prevent the release of radioactive fission products, requiring its structural integrity to be maintained throughout the whole operation period of nuclear reactor. Therefore, cladding failure due to PCI (pellet claading mechanical interaction) should be avoided as much as possible in fuel design and operating conditions. At the same time, it is necessary to achieve effective control of the cladding stress by limiting the power growth rate etc. However, in the manufacturing process of fuel rod, the MPS (missing pellet surface) defect is inevitably generated. This defect may lead to a substantial increase in the local stress of the cladding, which in turn exceeds its corresponding stress limit, resulting in cladding failure. Accurate simulation of fuel performance caused by such defects will help prevent such failures. The traditional fuel performance analysis codes are based on a 1.5D analysis framework and cannot handle the local asymmetry problem of fuel such as the MPS defect. In order to accurately simulate the PCI phenomenon caused by the MPS defect, this research establishes a fuel performance analysis code based on the ABAQUS software and this code is suit for the 2D and 3D conditions. Based on the established analysis code, the irradiation-thermal-mechanical behavior of nuclear fuel under typical II transient conditions was studied, and the sensitivity analysis of the influence of different MPS sizes on the local stress of cladding was carried out. The simulation results show that :(1)the mises stress, contact pressure and equivalent creep strain of the cladding may be unevenly distributed due to the MPS defect.(2)the MPS defect will result in a more severe contact pressure on cladding during power transient period, which may lead to failure of cladding and should be prevented. The simulation method established in this research could be very help for the performance analysis for the nuclear fuel rods.

scholarly journals Development of coupled neutronics and fuel performance analysis capabilities between Serpent and TRANSURANUS

2020 ◽  
Vol 359 ◽  
pp. 110450
Author(s):  
Heikki Suikkanen ◽  
Ville Rintala ◽  
Arndt Schubert ◽  
Paul Van Uffelen
Keyword(s):  
Performance Analysis ◽  
Fuel Performance

Sensitivity analysis of fuel pin failure performance under slow-ramp type transient overpower condition by using a fuel performance analysis code FEMAXI-FBR

2012 ◽  
Vol 49 (10) ◽  
pp. 975-987 ◽  
Author(s):  
Yasushi Tsuboi ◽  
Hiroshi Endo ◽  
Tomoko Ishizu ◽  
Isao Tatewaki ◽  
Hiroaki Saito ◽  
...  
Keyword(s):  
Sensitivity Analysis ◽  
Performance Analysis ◽  
Fuel Performance ◽  
Fuel Pin

scholarly journals PENGARUH VARIASI MAIN JET NOZZEL PADA SISTEM KARBURATOR TERHADAP UNJUK KERJA MESIN

POROS ◽  
2017 ◽  
Vol 13 (2) ◽  
pp. 51
Author(s):  
Alvinsen Alfonso ◽  
Abrar Riza ◽  
I Made Kartika
Keyword(s):  
Performance Analysis ◽  
Energy Conversion ◽  
Fuel Consumption ◽  
Mechanical Engineering ◽  
Motor Fuel ◽  
Nozzle Diameter ◽  
Fuel Performance ◽  
Maximum Performance ◽  
Load Variations ◽  
Jet Nozzle

Abstract: This study discusses the effect of variations in the diameter of the main jet nozzles on the performance of the motor fuel. Performance analysis covering torque, power and specific fuel consumption (sfc). With the aim to determine the maximum performance that can be generated on any variation of the diameter of the main jet nozzles. At the time of this experiment performed with the engine 4 stroke Honda GX-160, using hydro tool dynamometer and using premium fuel. The data taken is the engine rotation, the force measured on the dynamometer and the time spent fuels. Tests conducted at the Laboratory of Energy Conversion Mechanical Engineering UNTAR Jakarta. Testing is done by providing the machine with a load variation of rotation remains in order to obtain a force on each spin machine with a main jet nozzle diameter variations. Variations rev the engine starts at the minimum rotation until maksimuml with fixed load, variations in the diameter of the main jet nozzles on testing. 

Fission Product Release From HTGR Fuel Under Core Heatup Accident Conditions

2008 ◽  
Author(s):  
Karl Verfondern ◽  
Heinz Nabielek
Keyword(s):  
Fission Product ◽  
Technology Development ◽  
Normal Operation ◽  
Fuel Performance ◽  
Heating Facility ◽  
Product Release ◽  
Essential Input ◽  
Accident Conditions ◽  
Product Species ◽  
Htgr Fuel

Various countries engaged in the development and fabrication of modern fuel for the High Temperature Gas-Cooled Reactor (HTGR) have initiated activities of modeling the fuel and fission product release behavior with the aim of predicting the fuel performance under operating and accidental conditions of future HTGRs. Within the IAEA directed Coordinated Research Project CRP6 on “Advances in HTGR Fuel Technology Development” active since 2002, the 13 participating Member States have agreed upon benchmark studies on fuel performance during normal operation and under accident conditions. While the former has been completed in the meantime, the focus is now on the extension of the national code developments to become applicable to core heatup accident conditions. These activities are supported by the fact that core heatup simulation experiments have been resumed recently providing new, highly valuable data. Work on accident performance will be — similar to the normal operation benchmark — consisting of three essential parts comprising both code verification that establishes the correspondence of code work with the underlying physical, chemical and mathematical laws, and code validation that establishes reasonable agreement with the existing experimental data base, but including also predictive calculations for future heating tests and/or reactor concepts. The paper will describe the cases to be studied and the calculational results obtained with the German computer model FRESCO. Among the benchmark cases in consideration are tests which were most recently conducted in the new heating facility KUEFA. Therefore this study will also re-open the discussion and analysis of both the validity of diffusion models and the transport data of the principal fission product species in the HTGR fuel materials as essential input data for the codes.

Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT

2018 ◽  
Author(s):  
Jian Li ◽  
Ding She ◽  
Lei Shi ◽  
Jing Zhao
Keyword(s):  
Performance Analysis ◽  
Mechanical Performance ◽  
Performance Model ◽  
Fuel Performance ◽  
Triso Fuel ◽  
Coated Particle ◽  
First Results ◽  
Fuel Particles ◽  
Accident Conditions ◽  
Radioactivity Retention

Tristructural isotropic (TRISO) fuel particles are chosen as the major fuel type of High temperature gas cooled reactor (HTGR). The TRISO coated particle also acts as the first barrier for radioactivity retention. The performance of the TRISO coated particle has a significant influence on the safety of HTGR. A set of fuel performance analysis codes have been developed during the past decades. The main functions of these codes are conducting stress calculation and failure probability prediction. PANAMA is a widely used German version fuel performance analysis code, which simulates the mechanical performance of TRISO coated particle under normal and accident conditions. In this code, only a simple pressure vessel model is considered, which is insufficient in stress analysis and fuel failure rate prediction. Nowadays, efforts have been done to update the fuel performance model utilized in PANAMA code, and a new TRISO fuel performance analysis code, FFAT, is under developed. This paper describes the newly updated TRISO fuel performance model and presents some first results based on the updated model.

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