scholarly journals ILT15 - A Computer Program for Evaluation of Accelerated Leach Test Data of LLW in the Hungarian NPP Paks

2018 ◽  
Author(s):  
György Pátzay ◽  
Ottó Zsille ◽  
József Csurgai ◽  
Árpád Nényei ◽  
Ferenc Feil ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Computer Program ◽  
Mathematical Models ◽  
Test Data ◽  
Source Term ◽  
Infinite Medium ◽  
Finite Cylinder ◽  
Programming Environment ◽  
Waste Forms ◽  
Leach Test

Computer Program ILT15 developed to accompany a new leach test for solidified radioactive waste forms in the Hungarian NPP Paks. The program is designed to be used as a tool for performing the calculations necessary to analyse leach test data, a modelling program to determine if diffusion is the operating leaching mechanism (and, if not, to indicate other possible mechanisms), and a means to make extrapolations using the diffusion models. The ILT15 program contains four mathematical models that can be used to represent the data, diffusion through a semi-infinite medium, diffusion through a finite cylinder, diffusion plus partitioning of the source term and solubility limited leaching. The program is written in C++ in the Borland C++ Builder programming environment. A detailed description of application of this modelling computer program is given.

scholarly journals ILT20 – an Upgraded Computer Program for Evaluation of Accelerated Leach Test Data of LLW in the Hungarian NPP Paks

2021 ◽  
Author(s):  
György Pátzay ◽  
János Nyőgér ◽  
Ottó Zsille ◽  
József Csurgai ◽  
Ferenc Feil ◽  
...  
Keyword(s):  
Differential Equation ◽  
Partial Differential Equation ◽  
Computer Program ◽  
Test Data ◽  
Computational Algorithm ◽  
Cylindrical Specimen ◽  
Accurate Method ◽  
Programming Environment ◽  
Waste Forms ◽  
Leach Test

Computer Program ILT15 was earlier developed to accompany a new leach test for solidified radioactive waste forms in the Hungarian NPP Paks. The program was designed to be used as a tool for performing the calculations necessary to analyze leach test data, a modelling program to determine if diffusion is the operating leaching mechanism (and, if not, to indicate other possible mechanisms), and a means to make extrapolations using the diffusion models. The program uses computational algorithm of ASTM C1308 standard. Now we have developed another computational algorithm based on a Partial Differential Equation (PDE) of a cylindrical specimen, solved the PDE by a Crank-Nicolson Finite Difference Method (FDM) and calculated by integration the eluted amount of a given component in time. The new solution more accurate method was integrated into the existing ILT15 computer program and the resulting new ILT20 program is able to calculate the Incremental/Cumulative Fraction Leached IFL/CFL) either by ASTM or PDE numerical solution methods.ILT20 program is written in C++ in the Borland C++ Builder programming environment. A detailed description of application of this upgraded modelling computer program is given.

Geochemically derived non-gaseous radionuclide source term for the Asse salt mine – assessment for the use of a Mg(OH)2-based backfill material

2004 ◽  
Vol 92 (9-11) ◽  
Author(s):  
Volker Metz ◽  
W. Schüßler ◽  
B. Kienzler ◽  
Thomas Fanghänel
Keyword(s):  
Radioactive Waste ◽  
Waste Disposal ◽  
Source Term ◽  
Geochemical Modeling ◽  
Test Site ◽  
Radioactive Waste Disposal ◽  
Salt Mine ◽  
Waste Forms ◽  
Radionuclide Inventory ◽  
Radionuclide Source

SummaryThe Asse salt mine was used as a test site for radioactive waste disposal from 1967 to 1978. Low- and intermediate-level waste forms (LLW/ILW) were emplaced, containing a total radionuclide inventory of 3×10Geochemical modeling leads to the conclusion that Portland cement, a Mg(OH)

scholarly journals Accelerated Leach Test for Low-level Radioactive Waste Forms in the Hungarian NPP Paks

2017 ◽  
Vol 07 (04) ◽  
Author(s):  
Gyorgy Patzay ◽  
Otto Zsille ◽  
Jozsef Csurgai ◽  
Gyula Vass ◽  
Ferenc Feil
Keyword(s):  
Radioactive Waste ◽  
Low Level ◽  
Waste Forms ◽  
Leach Test ◽  
Low Level Radioactive Waste

The use of zeolites for the treatment of radioactive waste

1985 ◽  
Vol 49 (351) ◽  
pp. 203-210 ◽  
Author(s):  
A. Dyer ◽  
K. Y. Mikhail
Keyword(s):  
Heat Treatment ◽  
Radioactive Waste ◽  
Test Data ◽  
Synthetic Zeolite ◽  
Cement Composites ◽  
Zeolite A ◽  
Mild Heat ◽  
Zeolite Structure ◽  
Leach Test ◽  
Leaching Experiments

AbstractThe uptake of 137-Cs and 90-Sr on to synthetic zeolite A has been studied. The use of a combined barium exchange followed by a relatively mild heat treatment has been shown to fix the isotopes within a collapsed zeolite structure. Leaching experiments using deionized and simulated sea and pond waters were carried out on zeolite compacts and zeolite/cement composites. They demonstrated the effectiveness of the calcination and cement containment. Some comments on the interpretation of leach test data are made.

Accelerated leach test for low-level radioactive waste forms in the Hungarian NPP Paks

2019 ◽  
Vol 24 (3) ◽  
pp. 302
Author(s):  
Ferenc Feil ◽  
György Pátzay ◽  
Ottó Zsille ◽  
Jozsef Csurgai ◽  
Gyula Vass
Keyword(s):  
Radioactive Waste ◽  
Low Level ◽  
Waste Forms ◽  
Leach Test ◽  
Low Level Radioactive Waste
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