Internal Dose Assumptions: NORM

[BLReider@AOL.COM]

I am interested in finding out what assumptions others use when calculating internal dose from processed U and Th tailings/sludge material.  We have limited test information on solubility and particle size.



1.  What assumptions about solubility of radionuclides are used when limited information is available?  



Do you follow the solubility of the parent if no additional information is present?  For example, if you have information about uranium being insoluble, but radium being Class W (or medium clearance), but no information about daughters of radium, do you follow the solubility of radium for all radium daughters and the solubility of uranium for all uranium daughters?



Are there any references that give information that can be used to make assumptions about solubility on an elemental basis?  



2.  What assumptions are commonly used about the soil particulate concentrations of radionuclides below radon on the decay chain?  For example, some Rn decays while in the soil.  An example of this is R-219 which has a 4 sec half life.  One would expect the Rn-219 daughters to be present in soil in equilibrium with Ac-227.  



3.  What DACs are used for Po-215 and Bi-211 in air from soil?  Do you use the 10CFR20 value for alpha emitters not listed in Appendix B? 



Thanks in advance.

Barbara Reider, CHP

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