L - KTH
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L - KTH
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60 C.J. Wooo<br />
6.9 Complications encountered with the cement solidification of spent resins<br />
In a recent EPRI seminar, the subject of waste solidification, packaging and burial took<br />
center stage in view of field experience from reactor decontamination activities (51-53).<br />
The Nuclear Regulatory Commission seminar participants made several key observations that<br />
warrant mentioning. Over the past couple of years there have been several incidents where<br />
problems have been encountered with cement solidified wastes. These incidents include<br />
problems with expansion, disintegration, non-solidlflcatlon, and overly-rapld<br />
solidification of cement solidified waste forms. Examples are (I) the cracking and<br />
splitting of two liners at Three Mile Island (caused by expansion and disintegration of the<br />
cement-solldlfled bead resin waste); (2) expansion of a liner containing cement-solldlfled<br />
LOMI decontamination waste on bead resin at Millstone; (3) non-solldlflcatlon of LOMI-<br />
decontamination waste (on resin beads) at Fitzpatrick; (4) too-rapid solidification<br />
(occurring before the prescribed amount of cement could be added to the mix) st Quad<br />
Cities; and (5) excessive foaming (due to detergent "impurities") at Sequoyah.<br />
Contributing factors in these cases appear to include the following:<br />
Excessive loading (as a fraction of the total volume of the waste form) of bead<br />
resin.<br />
The presence of decontamination solution chemicals.<br />
The presence of ingredients ("impurities") in the waste stream that were not<br />
tested in the laboratory development of the waste formulation or recipe.<br />
A lack of knowledge by the waste generator/processor of what specific composition<br />
is being processed.<br />
The potential impact of this situation on the future use of cement for low-level waste<br />
stabilization is that NRC may take certain actions in the near future. First, at least for<br />
certain troublesome waste streams such as those involving bead resins and decontamination<br />
chemicals, waste loadings will have to be significantly reduced. In some cases, the<br />
current waste loading approach 70 to 80 percent by volume of the waste; that is, cement<br />
comprises only 20 percent by volume of waste form. Thus, there is simply too little<br />
cementitiOus material available to bind the waste together and to provide the required<br />
structural stability. The approach taken toward qualifying the waste formulation, or<br />
recipe, has been essentially empirical and is not one that is primarily based on a precise<br />
scientific understanding of the fundamental mechanisms involved. Some margin must be<br />
provided to compensate for effects that are not addressed in the laboratory testing where<br />
PCP data are generated.<br />
A second approach that should help to reduce the llkellhood of encountering problems in<br />
producing stable solidified waste forms is to improve the waste handling end<br />
characterization. Though some utilities are doing well in that regard, it is clear that in<br />
some cases the wastes are being handled in a manner that can lead to solidification<br />
problems. Examples include situation where wastes from different waste streams are placed<br />
in the same tank and where adequate analyses of the resultant mix of wastes are not<br />
obtained prior to processing. A few hundred parts per million of ingredient can have a<br />
drastic effect on the set time and ultlmate solidification of a cement waste form.<br />
A third approach that should be investigated further involves the chemical or thermal<br />
treatment of the waste material, particularly bead resin material, to render it move<br />
resistant to interaction with the cementltlous material. An example of such a process is<br />
one that is used in Sweden, where certain resins wastes are heated to 150 degrees Celsius<br />
for ten to fifteen hours, as a pretreatment before solidification in cement. The volume of<br />
organic ion exchange resins is reduced by loss of interstitial and internal water by the<br />
heat treatment. Thermal decomposition of the quaternary ammonium groups produces a reduced<br />
tendency to swell when wetted.<br />
Recent attempts to solldlfy waste resins generated from reactor system decontamination<br />
provided an opportunity to study the cementation process more closely (5_~4). The genesis of<br />
the problem is believed to be the introduction of weak anion resin Ionac A-365 with a<br />
capacity 2.5 times that of anion resins used in the past to remove plcollnlc acid from LOMI<br />
streams (I0). A "solidlfled" llner was found to contain serious nonhomogeneltles, sample<br />
portions showing large concentrations of resin not set into cement.