scholarly journals Sensitivity and uncertainty analyses applied to one-dimensional radionuclide transport in a layered fractured rock: Evaluation of the Limit State approach, Iterative Performance Assessment, Phase 2

1992 ◽  
Author(s):  
Y.T. Wu ◽  
A.B. Gureghian ◽  
B. Sagar ◽  
R.B. Codell
Keyword(s):  
Performance Assessment ◽  
Fractured Rock ◽  
Limit State ◽  
Radionuclide Transport ◽  
Phase 2 ◽  
One Dimensional ◽  
Uncertainty Analyses

Identification of sorption processes and parameters for radionuclide transport in fractured rock

2012 ◽  
Vol 414-415 ◽  
pp. 220-230 ◽  
Author(s):  
Zhenxue Dai ◽  
Andrew Wolfsberg ◽  
Paul Reimus ◽  
Hailin Deng ◽  
Edward Kwicklis ◽  
...  
Keyword(s):  
Fractured Rock ◽  
Radionuclide Transport

One-dimensional model analysis and performance assessment of Tesla turbine

2018 ◽  
Vol 134 ◽  
pp. 546-554 ◽  
Author(s):  
Jian Song ◽  
Xiao-dong Ren ◽  
Xue-song Li ◽  
Chun-wei Gu ◽  
Ming-ming Zhang
Keyword(s):  
Performance Assessment ◽  
Model Analysis ◽  
Dimensional Model ◽  
One Dimensional ◽  
And Performance

Study of the sorption and modelling of cesium by a Brazilian bentonite using PHREEQC

MRS Advances ◽  
2020 ◽  
Vol 5 (5-6) ◽  
pp. 245-252
Author(s):  
Clédola C. O. de Tello ◽  
Daisy M. M dos Santos ◽  
Thais B. Teixeira
Keyword(s):  
Diffusion Coefficient ◽  
Flow Cell ◽  
Batch Adsorption ◽  
Radionuclide Transport ◽  
One Dimensional ◽  
Cesium Sorption ◽  
Dimensional Flow ◽  
Retardation Coefficient ◽  
Cesium Radionuclide

ABSTRACTTo estimate the cesium sorption by the bentonite and to obtain the isotherms, some batch-adsorption experiments are being carried out, being the Kd (retardation coefficient) calculated from these isotherms. One-dimensional flow cell was constructed to measure the bentonite permeability regarding to a cesium solution, which results will be used to evaluate the diffusion coefficient – D. It will be used the PHREEQC software to model the transport of the cesium radionuclide through this bentonite with the Kd and D data. The modelling of radionuclide transport in the Brazilian materials will contribute to evaluate the efficiency of multi-barriers system of the national repository, because it is one of its safety criteria.

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