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
Author(s):  
Changbing Tang ◽  
Yongjun Jiao ◽  
Yuanming Li ◽  
Yi Zhou ◽  
Kun Zhang

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.


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

POROS ◽  
2017 ◽  
Vol 13 (2) ◽  
pp. 51
Author(s):  
Alvinsen Alfonso ◽  
Abrar Riza ◽  
I Made Kartika

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. 


Author(s):  
Jian Li ◽  
Ding She ◽  
Lei Shi ◽  
Jing Zhao

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.


2015 ◽  
Vol 84 ◽  
pp. 98-110 ◽  
Author(s):  
J.D. Hales ◽  
M.R. Tonks ◽  
F.N. Gleicher ◽  
B.W. Spencer ◽  
S.R. Novascone ◽  
...  

Sign in / Sign up

Export Citation Format

Share Document