An adaptive regularized iterative FBP algorithm with high sharpness for irradiated fuel assembly reconstruction from few projections in FNCT

2020 ◽  
Vol 145 ◽  
pp. 107515
Author(s):  
Sangang Li ◽  
Zhengyun Dong ◽  
Quan Gan ◽  
Jing Song ◽  
Qi Yang
2017 ◽  
Vol 727 ◽  
pp. 693-697
Author(s):  
Yan Hua Peng ◽  
Fei Wang ◽  
Wei Zhu ◽  
Yan Jiang ◽  
Hong Kui Tang ◽  
...  

UO2 fuel pellets may be swelling and recrystallization during irradiation. Density, dimension and distribution of pores are main factors to induce irradiation swelling, especially the size distribution of pellet pores plays an important role. 4×4-4 fuel assembly was a high performance fuel assembly which was self-designed and manufactured, the average burn-up of the fuel assembly was 42GWd/tU.For studying the effect of irradiation on pore modality, the specimens of irradiated UO2 fuel pellets were taken from 4×4-4 fuel assembly after dismantling, microscopic structure and distribution of pores for UO2 fuel assembly by scanning electron microscopy were studied in this paper. The results showed that there were many cracks in fuel pellets, most micro-cracks were transgranular crack. The release rate of fission gas with burn up were augmentation, which was consistent with the porosity of diversity burp up fuel rod. Pores were distributed non-uniformly in irradiated fuel pellets, gathered at local area and more obvious connectivity of pores. The size of pores after the irradiation was between 0.2~1.2 μm, and mostly distributed at 0.3μm ~0.6 μm; The pores at grain boundary of two adjacent grains was less, the pores at grain boundary were distributed by the way of triangle or quadrilateral. The size of pores was increased than pre-irradiation, but ratio of pores and density of pores were decreased obviously, the phenomenon of irradiation densification was occurred in fuel pellets after irradiated. Recrystallization and Rim structure effect were not found.


Author(s):  
D. S. Lawson

Careful consideration of the requirements for an A.G.R. fuelling system leads to the adoption of a fuelling machine capable of handling a single fuel assembly and a short shielded sealing plug. Examination of active handling and maintenance leads to a combination of several functions in one facility in order to save cost. Dry storage of irradiated fuel is preferable to storage in a pond.


2019 ◽  
Vol 9 (2) ◽  
pp. 1-9
Author(s):  
Branislav Vrban ◽  
Štefan Čerba ◽  
Jakub Lüley ◽  
Filip Osuský ◽  
Mikuláš Vorobeľ ◽  
...  

The paper investigates various computational modelling issues associated with VVER-440 fuel depletion, relevant to burnup credit. The SCALE system and the TRITON sequence are used for the calculations. The effects of variations in depletion parameters and used calculation methods on the isotopic vectors are investigated. The burnup behaviour of Gadolinium is quite important in actual core analysis, but its behaviour is somewhat complicated, requiring special treatment in numerical modelling and calculations. Therefore, a special part of the paper is devoted to the treatment of Gadolinium-bearing fuels. Moreover, some discussions on power normalization are also included. To assess the acquired modelling experience used to predict the VVER-440 spent fuel nuclide composition, the measured compositions of Novovoronezh NPP irradiated fuel assembly are compared to data calculated by TRITON sequence. The samples of fuel assembly with 3.6 wt. % U-235 enrichment underwent 4-cycle campaign of totally 1109 effective full power days in the core and cooling period of 1-13 years. Calculated concentrations are compared to measured values burdened with their experimental uncertainties for totally 47 nuclides. The calculated results show overall a good agreement for all nuclides, differences from measured are pointed out and discussed in the paper.


2017 ◽  
Vol 2017 (2) ◽  
pp. 38-50
Author(s):  
Maya Yurievna Kalenova ◽  
Aleksey Vladilenovich Ananiev ◽  
Petr Borisovich Baskov ◽  
Sergey Vyacheslavovich Sklyarov

2012 ◽  
Vol 1475 ◽  
Author(s):  
Kozo Katsuyama ◽  
Akihiro Ishimi ◽  
Koji Maeda ◽  
Tsuyoshi Nagamine ◽  
Takeo Asaga

ABSTRACTIn order to observe the structural change in the interior of irradiated fuel assembly, the non-destructive post irradiation examination technique using X-ray computer tomography (X-ray CT) was developed.In this X-ray CT system, the 12 MeV X-ray pulses were used in synchronization with the switch-in of the detector in order to minimize the effects of the gamma ray emissions from the irradiated fuel assembly then clear cross section CT image of irradiated fuel assembly could be successfully obtained. Also, this non-destructive technique can be applied to observe the inner condition of the high radioactive materials such as a radioactive waste.


2011 ◽  
pp. 107-114
Author(s):  
B. Lacroix ◽  
T. Martella ◽  
M. Pras ◽  
M. Masson-Fauchier ◽  
L. Fayette

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