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.

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.

Effect of Fe2O3/ZnO on Two Glass Compositions for Solidification of Swedish Nuclear Wastes

1981 ◽  
Vol 11 ◽  
Author(s):  
J. L. Nogues ◽  
L. L. Hench
Keyword(s):  
Nuclear Waste ◽  
Glass Surface ◽  
Fission Products ◽  
Waste Glass ◽  
Nuclear Wastes ◽  
Leaching Behavior ◽  
Waste Products ◽  
Simulated Waste ◽  
Nuclear Waste Glass ◽  
Glass Compositions

A recent study concluded that addition of Fe203 to a soda borosilicate nuclear waste glass may significantly reduce damage by water attack due to formation of a Fe-rich film on the glass surface. However, differences in SiO2, B203, CaO, and concentration of fission products in previous glass compositions make it impossible to ascribe the improved leach resistance solely to Fe203 content. In the present work, leaching behavior of two glasses are compared which differ only by the substitution of Fe203 for some of the ZnO in the glass. Both glass compositions, Table 1, are compatible with the French AVM process and contain 9% (by weight) of simulated waste products characteristic of the Swedish nulcear waste program.

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.

Separation of gaseous fission products from reactor and reprocessing-plant off-gases

1978 ◽  
Vol 12 (1) ◽  
pp. 85-88 ◽  
Author(s):  
S. G. Mastera ◽  
M. Laser ◽  
E. Merz
Keyword(s):  
Fission Products ◽  
Gaseous Fission ◽  
Reprocessing Plant

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

A gas-jet recoil-transport system for fission products and its application to a continuous chemical separation procedure in the gas phase

1977 ◽  
Vol 147 (2) ◽  
pp. 371-378 ◽  
Author(s):  
R.J. Silva ◽  
N. Trautmann ◽  
M. Zendel ◽  
P.F. Dittner ◽  
E. Stender ◽  
...  
Keyword(s):  
Gas Phase ◽  
Transport System ◽  
Fission Products ◽  
Chemical Separation ◽  
Gas Jet ◽  
Separation Procedure ◽  
Continuous Chemical
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