Glasses suitable for the long-term storage of fission products

Author(s):  
J.R. Grover ◽  
B.E. Chidley
2002 ◽  
Vol 713 ◽  
Author(s):  
Marsha J. Lambregts ◽  
Steven M. Frank

ABSTRACTArgonne National Laboratory has developed an electrometallurgical treatment for DOE spent metallic nuclear fuel. Fission products are immobilized in a durable glass bonded sodalite ceramic waste form (CWF) suitable for long term storage in a geological repository. Cesium is estimated to be in the waste form at approximately 0.1 wt.%. The exact disposition of cesium was uncertain and it was believed to be uniformly distributed throughout the waste form. A correlation of X-ray diffractometry (XRD), electron microscopy (EM), and nuclear magnetic resonance spectroscopy (NMR) performed on surrogate ceramic waste forms with high cesium loadings found a high cesium content in the glass phase and in several non-sodalite aluminosilicate phases. Cesium was not detected in the sodalite phase.


1980 ◽  
Vol 35 (2) ◽  
pp. 171-179 ◽  
Author(s):  
J. C. Ruffenach ◽  
R. Hagemann ◽  
E. Roth

AbstractThe Oklo natural nuclear reactors have been studied mainly by isotopic and chemical analyses of uranium and fission products. Interpretation of these analyses allows parameters which characterize these reactions (flux, fluence,...), and also the age and duration of the nuclear reactions to be evaluated. The mechanisms and extent of fission-product migration can also be discussed. The behaviour of various elements formed in the Oklo uraninite and in oxyde fuels of pressurized water reactors is compared and found to be similar. Therefore, experience gained from the study of the Oklo phenomenon can provide valuable information on the long-term storage of radioactive wastes in geological media.


Author(s):  
Carol M. Jantzen

The long radioactive lifetime of the fission products in nuclear wastes requires that the materials be isolated from the biosphere for periods of 103 to 105 years. One method of accomplishing this is to consolidate the waste into a chemically stable solid form and to contain this within a multiple barrier canister which can be transported to a geologically stable repository for long-term storage. A number of candidate solid waste forms are being assessed to determine their suitability for incorporating various nuclear waste compositions and they include borosilicate glass (the current reference form), ceramics, high silica glasses, and cement.


2002 ◽  
Vol 757 ◽  
Author(s):  
A. V. Ochkin ◽  
S. V. Stefanovsky ◽  
S. I. Rovny

ABSTRACTHLW after the separation of U, Pu and Np contains two major radionuclide groups: fission products and TRU elements. The later ones are the most dangerous and should be separated in the special actinide fraction. This process has been realized at PA “Mayak”.The composition of the actinide fraction depends on a separation method:A. Radionuclides of Am and Cm with minor amounts of U, Np and Pu.B. Radionuclides of Am and Cm with minor amounts of U, Np and Pu and also REEs.C. Radionuclides of Am and Cm with minor amounts of U, Np and Pu and also REEs and perhaps some amount of Zr.The fraction with composition A can be burned off in fast reactors whereas the fractions with compositions B and C should be immobilized in stable matrices. Alpha-Activity of actinide fraction is subsequently determined by 244Cm, 241Am, 244Am, 239Pu and 242Pu during a long-term storage. The storage time depends on conditions and can reach several hundreds of thousands years. The main requirements to matrices are chemical and radiation resistances. The fraction with composition B can be incorporated in perovskite ceramics whereas in case of composition C the additional zirconolite and/or pyrochlore phases are necessary.


1983 ◽  
Vol 26 ◽  
Author(s):  
M. Kubota ◽  
I. Yamaguchi ◽  
K. Okada ◽  
Y. Morita ◽  
K. Nakano ◽  
...  

ABSTRACTRemoval of the long-lived radionuclides from high-level waste (HLW) is a potential means not only for making wastes more acceptable in terms of long term hazards, but also for alleviating storage requirement. From these points, the authors are developing a method of partitioning actinides, Sr-90 and Cs-137 from HLW. A chemical flow-sheet has been constructed and experiments with actual HLW were initiated in 1982. Through the partitioning, active elements in HLW can be fractionated into 3 groups. Total volume of the solid materials of the 3 groups was calculated and found to be reduced to less than one-third of the volume of the vitrified material containing 10 wt% of fission products as oxide. Such volume reduction seems to facilitate the long term storage or the deep geological disposal of HLW.


Author(s):  
Yvon Vanderborck ◽  
Jacques Basselier

Abstract Long term storage of plutonium separated from fission products is not a good solution according to the current non-proliferation criteria as well as from an economic point of view. This material has thus to be converted to the equivalent of the “spent fuel standard”. Only one technique has so far reached the industrial maturity necessary to convert the important existing plutonium stockpiles: it is the use of plutonium to manufacture and irradiate MOX fuel. The paper reviews the existing information over the separated plutonium stockpiles and the various International Agreements, which are implemented to cover the peaceful use of plutonium. The dual track solution retained in U.S. in mentioned. The situation U.S. and Russia is updated, the roles of Europe and Belgium are presented. The activities of BELGONUCLEAIRE on the US and Russian sides will be described and its experience in fabrication technology, quality, safety, environmental issues, non-proliferation, safeguards and transport will be considered. The transfer of technology to France, Japan and US makes the MIMAS BELGONUCLEAIRE fabrication process equivalent to an international standard. This forms a sound basis for further development and for a transfer to Russia. The paper will demonstrate by this way the commitment of BELGONUCLEAIRE to participate to the peaceful uses of plutonium, as well as its contribution safely to non-proliferation and disarmament international policy.


2001 ◽  
Vol 6 (2) ◽  
pp. 3-14 ◽  
Author(s):  
R. Baronas ◽  
F. Ivanauskas ◽  
I. Juodeikienė ◽  
A. Kajalavičius

A model of moisture movement in wood is presented in this paper in a two-dimensional-in-space formulation. The finite-difference technique has been used in order to obtain the solution of the problem. The model was applied to predict the moisture content in sawn boards from pine during long term storage under outdoor climatic conditions. The satisfactory agreement between the numerical solution and experimental data was obtained.


Diabetes ◽  
1997 ◽  
Vol 46 (3) ◽  
pp. 519-523 ◽  
Author(s):  
G. M. Beattie ◽  
J. H. Crowe ◽  
A. D. Lopez ◽  
V. Cirulli ◽  
C. Ricordi ◽  
...  

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