Leaching Behavior of Simulated Radioactive Waste Glass by Neutron Activation Method

1983 ◽  
Vol 26 ◽  
Author(s):  
Seichi Sato ◽  
Hirotaka Furuya ◽  
Kazuaki Ohta ◽  
Masayasu Sugisaki ◽  
Tadaharu Tanai
Keyword(s):  
Radioactive Waste ◽  
Mass Loss ◽  
Nuclear Reactor ◽  
Solution Concentration ◽  
Waste Glass ◽  
Absorption Analysis ◽  
Leaching Behavior ◽  
Alkali Ions ◽  
Displacement Per Atom ◽  
Elemental Mass

ABSTRACTSimulated radioactive waste glass was irradiated in a nuclear reactor and radiation damage was induced by 10B(n,0)7Li reaction up to 0.14 displacement per atom. Static leach tests of the activated waste glass were carried out at 40°C, up to 38 days. Concentration of elements in leachate was determined by gamma-spectrometry. The leach test of non-irradiated glass was also performed at 40°C up to 82 days in which the solution concentration of elements was determined by an atomic absorption analysis. Leach results are given in terms of normalized elemental mass loss for the seven elements Na, K, Cs, Ca, Zn, La and Ce. Normalized elemental mass loss of alkali ions was proportional to square root of time and then, was proportional to time. Normalized elemental mass loss of alkali earth ions did not show such a simple tendency. Build up of zinc on the waste glass surface was observed following its initial leaching. It was also found that theleach rate of Cs, Zn and Ce decreased with increase of irradiation exposure of waste glass.

Leaching of Am-241 from a Radioactive Waste Glass Corroded in the Presence of Stainless Steel Corrosion Products and/or Bentonite

1987 ◽  
Vol 112 ◽  
Author(s):  
Masaki Tsukamoto ◽  
Inga-Kari Björner ◽  
Hilbert Christensen ◽  
Hans-Peter Hermansson ◽  
Lars Werme
Keyword(s):  
Stainless Steel ◽  
Radioactive Waste ◽  
Mass Loss ◽  
Total Mass ◽  
Corrosion Behaviour ◽  
Steel Corrosion ◽  
Waste Glass ◽  
Corrosion Products ◽  
Total Mass Loss ◽  
Elemental Mass

AbstractThe release of Am-241 during corrosion of the radioactive waste glass, JSS-A, has been studied in the presence of corrosion products and/or uncom-pacted bentonite. The corrosion behaviour of Am-241 has been analyzed using gamma spectrometry. Adsorption of Am-241 on bentonite is observed in all cases. The contents of Am-241 in centrifuged leachates are in most cases less than 1/100 of total values. The normalized elemental mass loss of Am increases initially with corrosion time, and the values in the presence of bentonite and corrosion products are larger than those in the presence of bentonite alone. This tendency is in agreement with results previously found for other elements. The release of Am is low, only about 10–20 % of the corresponding total mass loss.

Static Leaching of Actinides and Fission Products from Fully Radioactive Waste Glass of Hllw Generated in Tokai Reprocessing Plant

1988 ◽  
Vol 127 ◽  
Author(s):  
K. Miyahara ◽  
T. Ashida ◽  
Y. Yusa ◽  
N. Sasaki ◽  
N. Tsunoda
Keyword(s):  
Radioactive Waste ◽  
Alpha Spectrometry ◽  
Fission Products ◽  
Chemical Separation ◽  
Waste Glass ◽  
Chemical Processing ◽  
Leaching Behavior ◽  
Processing Facility ◽  
Reprocessing Plant ◽  
Ceramic Melter

ABSTRACTFully radioactive waste glass of HLLW generated in Tokai Reprocessing Plant was produced by using a small Joule-heated ceramic melter at the Chemical Processing Facility (CPF), Tokai Works, PNC, Japan. Static leach tests using the glass were carried out in doubly distilled water for a period of up to three months at 30°C and 90 °C. Gamma spectrometry was performed to measure 134Cs, 137Cs and 60Co in the leachates. After the chemical separation of Cs isotopes in the leachates, it was newly possible to measure 125Sb, 144Ce, 154Eu and 155Eu. Alpha spectrometry was performed to measure 239Pu+240Pu, 241Am and 244Cm in the leachates. Adsorption of the actinides on the wall of the leach vessel was recognized in all cases. Leaching behavior of the measured radionuclides were evaluated by considering mass balance of the radionuclides which were leached.

Elemental mass loss in silicate minerals during x-ray analysis

1990 ◽  
Vol 48 (4) ◽  
pp. 804-805
Author(s):  
P.E. Champness ◽  
R.W. Devenish
Keyword(s):  
Mass Loss ◽  
Current Density ◽  
Damage Mechanism ◽  
Beam Current ◽  
Single Chain ◽  
Plagioclase Feldspar ◽  
X Ray ◽  
Alkali Ions ◽  
Structural Order ◽  
Sheet Silicate

It has long been recognised that silicates can suffer extensive beam damage in electron-beam instruments. The predominant damage mechanism is radiolysis. For instance, damage in quartz, SiO2, results in loss of structural order without mass loss whereas feldspars (framework silicates containing Ca, Na, K) suffer loss of structural order with accompanying mass loss. In the latter case, the alkali ions, particularly Na, are found to migrate away from the area of the beam. The aim of the present study was to investigate the loss of various elements from the common silicate structures during electron irradiation at 100 kV over a range of current densities of 104 - 109 A m−2. (The current density is defined in terms of 50% of total current in the FWHM probe). The silicates so far ivestigated are:- olivine [(Mg, Fe)SiO4], a structure that has isolated Si-O tetrahedra, garnet [(Mg, Ca, Fe)3Al2Si3AO12 another silicate with isolated tetrahedra, pyroxene [-Ca(Mg, Fe)Si2O6 a single-chain silicate; mica [margarite, -Ca2Al4Si4Al4O2O(OH)4], a sheet silicate, and plagioclase feldspar [-NaCaAl3Si5O16]. Ion- thinned samples of each mineral were examined in a VG Microscopes UHV HB501 field- emission STEM. The beam current used was typically - 0.5 nA and the current density was varied by defocussing the electron probe. Energy-dispersive X-ray spectra were collected every 10 seconds for a total of 200 seconds using a Link Systems windowless detector. The thickness of the samples in the area of analysis was normally 50-150 nm.

Use of residual waste glass in an alkali-activated binder – Structural characterization, environmental leaching behavior and comparison of reactivity

2020 ◽  
pp. 101903
Author(s):  
Abdelhadi Bouchikhi ◽  
Yannick Mamindy-Pajany ◽  
Walid Maherzi ◽  
Cyrille Albert-Mercier ◽  
Hamza El-Moueden ◽  
...  
Keyword(s):  
Structural Characterization ◽  
Waste Glass ◽  
Leaching Behavior ◽  
Alkali Activated

XAFS analysis of ruthenium in simulated iron phosphate radioactive waste glass

2021 ◽  
Vol 551 ◽  
pp. 120393
Author(s):  
Yoshihiro Okamoto ◽  
Hidekazu Kobayashi ◽  
Hideaki Shiwaku ◽  
Ken-ichi Sasage ◽  
Kiyoshi Hatakeyama ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Iron Phosphate ◽  
Waste Glass

Characterization of Changes in Properties and Microstructure of Glassy Polymeric Carbon Following Au Ion Irradiation

2009 ◽  
Vol 1215 ◽  
Author(s):  
Malek Amir Abunaemeh ◽  
Mohamed Seif ◽  
Young Yang ◽  
Lumin Wang ◽  
Yanbin Chen ◽  
...  
Keyword(s):  
Photoelectron Spectroscopy ◽  
Nuclear Reactor ◽  
Ion Irradiation ◽  
Pyrolytic Carbon ◽  
X Ray ◽  
Triso Fuel ◽  
Transmission Electron ◽  
Displacement Per Atom ◽  
Polymeric Carbon

AbstractThe TRISO fuel has been used in some of the Generation IV nuclear reactor designs [1,2]. It consists of a fuel kernel of UOx coated with several layers of materials with different functions. Pyrolytic carbon (PyC) is one of the materials in the layers. In this study we investigate the possibility of using Glassy Polymeric Carbon (GPC) as an alternative to PyC. In this work, we are comparing the changes in physical and microstructure properties of GPC after exposure to irradiation fluence of 5 MeV Au equivalent to a 1 displacement per atom (dpa) at samples prepared at 1000, 1500 and 2000°C. The GPC material is manufactured and tested at the Center for Irradiation Materials (CIM) at Alabama A&M University. Transmission electron microscopy (TEM), Rutherford backscattering spectroscopy (RBS), X-ray photoelectron spectroscopy (XPS) and Raman spectroscopy were used for the analysis.

Preparation and Characterization of Immobilizing Radioactive Waste Glass From Industrial Wastes

Silicon ◽  
2015 ◽  
Vol 9 (1) ◽  
pp. 117-130 ◽  
Author(s):  
N. A. El-Alaily ◽  
W. M. Abdallah ◽  
B. A. Sabrah ◽  
A. I. Saad
Keyword(s):  
Radioactive Waste ◽  
Waste Glass ◽  
Industrial Wastes

How to Simulate the Microstructure Induced by a Nuclear Reactor with an Ion Beam Facility : DART

2009 ◽  
Vol 1215 ◽  
Author(s):  
Laurence Luneville ◽  
David Simeone ◽  
Gianguido Baldinozzi ◽  
Dominique Gosset ◽  
yves serruys
Keyword(s):  
Cross Sections ◽  
Nuclear Reactor ◽  
Nuclear Reactions ◽  
Ion Beam ◽  
Fast Neutrons ◽  
Relaxation Processes ◽  
Pressurized Water ◽  
Water Reactors ◽  
Displacement Per Atom ◽  
The Impact

AbstractEven if the Binary Collision Approximation does not take into account relaxation processes at the end of the displacement cascade, the amount of displaced atoms calculated within this framework can be used to compare damages induced by different facilities like pressurized water reactors (PWR), fast breeder reactors (FBR), high temperature reactors (HTR) and ion beam facilities on a defined material. In this paper, a formalism is presented to evaluate the displacement cross-sections pointing out the effect of the anisotropy of nuclear reactions. From this formalism, the impact of fast neutrons (with a kinetic energy En superior to 1 MeV) is accurately described. This point allows calculating accurately the displacement per atom rates as well as primary and weighted recoil spectra. Such spectra provide useful information to select masses and energies of ions to perform realistic experiments in ion beam facilities.

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