scholarly journals Software Design Document for the AMP Nuclear Fuel Performance Code

2010 ◽  
Author(s):  
Bobby Philip ◽  
Kevin T Clarno ◽  
Bill Cochran
Keyword(s):  
Nuclear Fuel ◽  
Software Design ◽  
Fuel Performance ◽  
Design Document

Software Design Document for the Oceanographic and Atmospheric Master Library SURF 3.1 Forecasting Program

2000 ◽  
Author(s):  
Daniel A. Osiecki ◽  
Lari N. Migues ◽  
Marshall D. Earle ◽  
Y. L. Hsu
Keyword(s):  
Software Design ◽  
Design Document

Numerical verification of equilibrium thermodynamic computations in nuclear fuel performance codes

2011 ◽  
Vol 414 (3) ◽  
pp. 399-407 ◽  
Author(s):  
M.H.A. Piro ◽  
T.M. Besmann ◽  
S. Simunovic ◽  
B.J. Lewis ◽  
W.T. Thompson
Keyword(s):  
Nuclear Fuel ◽  
Numerical Verification ◽  
Equilibrium Thermodynamic ◽  
Fuel Performance ◽  
Thermodynamic Computations

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 Mechanistic materials modeling for nuclear fuel performance

2017 ◽  
Vol 105 ◽  
pp. 11-24 ◽  
Author(s):  
Michael R. Tonks ◽  
David Andersson ◽  
Simon R. Phillpot ◽  
Yongfeng Zhang ◽  
Richard Williamson ◽  
...  
Keyword(s):  
Nuclear Fuel ◽  
Fuel Performance ◽  
Materials Modeling

A review of TRISO-coated particle nuclear fuel performance models

Rare Metals ◽  
2006 ◽  
Vol 25 (6) ◽  
pp. 337-342 ◽  
Author(s):  
B LIU ◽  
T LIANG ◽  
C TANG
Keyword(s):  
Nuclear Fuel ◽  
Performance Models ◽  
Fuel Performance ◽  
Coated Particle
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