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ASTM Selected Technical Papers
Stabilization and Solidification of Hazardous, Radioactive, and Mixed Wastes: 3rd Volume
By
TM Gilliam
TM Gilliam
Editor
Search for other works by this author on:
CC Wiles
CC Wiles
Editor
Search for other works by this author on:
ISBN-10:
0-8031-2020-6
ISBN:
978-0-8031-2020-4
No. of Pages:
734
Publisher:
ASTM International
Publication date:
1996

An extensive study was carried out on the release of different contaminants from cement stabilized wastes. The goal of the work was to make a computer code, called RECOSTA (RElease of COntaminant from cement STAbilized wastes), to support (i) the comprehension of the chemical-physical phenomena which govern the leachability of various elements (to choose the best composition for the immobilization matrix) and (ii) the definition of the protocols for monitoring and controlling of the release of pollutants (which occurs when hazardous waste are disposed of in a landfill). To this end the following toxic elements, incorporated in different cement based systems, were leached according to ANSI/ANS 16.1: Cs(I), Cd(II), Co(II), Cu(II), Pb(II), Sr(II), Zn(II), Cr(III), Fe(III), Cr(VI).

1.
De Angelis
,
G.
,
Marchetti
,
A.
, and
Balzamo
,
S.
, “
Leach studies: the influence of various parameters on the leaching of Cesium from cemented BWR evaporator concentrates
”, 2nd International Conference on Stabilization/solidification of Hazardous, Radioaotive and Mixed Wastes, ASTM STP 1123,
Gilliam
,
T. M.
and
Wiles
,
C. C.
, Eds.,
American Society for Testing and Materials
,
Philadelphia
,
1992
, pp. 182–192.
2.
Balzamo
S.
,
De Angelis
G.
, and
Marchetti
A.
, “
Determination of experimental parameters for evaluating the release of contaminants and their interaction with the environment at a waste disposal site
”, Joint International Symposium on Environmental Conseqences of Hazardous Waste Disposal,
Stockolm, Sweden
, 27–31 May 1991, Vol.
1
, pp. 155–164.
3.
Van der Sloot
H.A.
, “
Leaching Behaviour of Waste and Stabilized Waste Materials; Characterization for Environmental Assessment Purpose
”,
Waste Management and Research
 0734-242X,
8
, pp.215–228,
1990
.
4.
Bird
R.B.
,
Stewart
W.E.
,
Lightfoot
E.N.
,
Transport Phenomena
,
Wiley & Sons
,
New York
,
1960
.
5.
ANSI/ANS 16.1,
Proposed Americal National Standard Measurement of Leachability for Solidified Low-Level Radioactive Wastes
,
Americal National Standard Institute
,
New York, NY
.
1981
.
6.
ISO 6961: Long-Term Leach Testing of Solified Radioactive Waste Forms
.
International Organization of Standardization
,
Geneva, Switzerland
,
1982
.
7.
Crank
J.
,
The Mathematics of Diffusion
,
Clarendon Press
,
Oxford
,
1975
.
8.
Atkinson
A.
,
Nickerson
A.K.
, “
The Diffusion of Ions Through water-saturated Cement
”,
Journal of Material Science
 0022-2461,
19
, pp. 3068–3078,
1984
.
9.
Atkinson
A.
,
Nelson
K.
,
Valentine
T.M.
, “
Leach Test Characterization of Cement-Based Nuclear Waste Forms
”,
Nuclear and Chemical Waste Management
,
6
, pp. 241–253,
1986
.
10.
Inou
T.
,
Tsukamoto
M.
,
Fukushima
M.
,
Kinoshita
M.
, “
Diffusion of Neptunium in Simulated High Level Waste Glass
”,
Journal of Nuclear Science and Technology
,
23
(
11
), pp. 992–1000,
1986
.
11.
Atkinson
A.
,
Nickerson
A.K.
, “
Diffusion and Sorption of Cesium, Strontium, and Iodine in Water-saturated Cement
”,
Nuclear Technology
,
81
, pp. 100–113,
1988
.
12.
Plecas
I.
,
Drjiaca
J.
,
Peric
A.
,
Kostaadinovic
A.
,
Glodic
S.
, “
Radionuclide Migration Through Porous Nuclear Waste Forms
”,
Radioactive Waste Management in the Nuclear Fuel Cycle
,
14
(
3
), pp. 195–205,
1990
.
13.
Barone
F.S.
,
Rowe
R.K.
,
Quingley
R.M.
, “
A Laboratory Estimation of Diffusion and Adsorption Coefficients for Several Volatile Organics in a Natural Clayey Soil
”,
Journal of Contamination and Hydrology
 0169-7722,
10
, pp. 225–250,
1992
.
14.
Karapetyans
M.Kh.
,
Chemical Thermodynamics
,
MIR Publishers
,
Moscow
,
1978
.
15.
Coté
P.L.
,
Bridle
T.R.
,
Benedek
A.
, “
An Approach for Evaluating Long Term Leachability from Measurement of Instrinsic Waste Properties
”, Third International Symposium on Industrial and Hazardous Waste,
Alexandria, Egypt
, June 24–27, 1985.
16.
Banba
T.
, “
Leaching Model of Nuclear Waste Glass
”,
Journal of Nuclear Science and Technology
,
23
(
12
), pp. 1075–1082.
17.
Stegemann
J.A.
,
Coté
P.L.
, “
Summary of an Investigation of Test Methods for Solidified Waste Evaluation
”,
Waste Management
,
10
, pp.41–52,
1990
.
18.
Eichholz
G.G.
,
Petelka
M.F.
,
Whang
J.
, “
Leaching and Migration of Low-Level Wastes Unsaturated Conditions
”,
Radioactive Waste Management in the Nuclear Fuel Cycle
,
14
(
4
), pp. 285–310,
1990
.
19.
Matsuzuru
H.
,
Suzuki
A.
, “
Modeling of Release of Radionuclides from an Engineered Disposal Facility for Shallow-land Disposal of Low-Level Radioactive Wastes
”,
Waste Management
,
9
, pp.45–56,
1989
.
20.
Pescatore
C.
, “
Improved Expressions for Modeling Diffusive, Fraction Cumulative Leaching from Finite-Size Waste Forms
”,
Waste Management
,
10
, pp. 155–159,
1990
.
21.
Pescatore
C.
, “
Leach Rate Expressions for Performance Assessment of Solidified, Low-Level Radioactive Waste
”,
Waste Management
,
11
, pp.223–229,
1991
.
22.
Ames
W.F.
,
Nonlinear Partial Differential Equations in Engineering
,
Academic Press
,
New York
,
1965
.
23.
Patankar
S.V.
,
Numerical Heat Transfer and Fluid Flow
,
McGraw-Hill
,
New York
,
1980
.
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