Leach test of cladding removal waste grout using Hanford groundwater [electronic resource]

This report describes laboratory experiments performed during 1986-1990 designed to produce empirical leach rate data for cladding removal waste (CRW) grout. At the completion of the laboratory work, funding was not available for report completion, and only now during final grout closeout activities...

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Bibliographic Details
Online Access: Online Access
Corporate Authors: Pacific Northwest Laboratory (Researcher), Pacific Northwest National Laboratory (U.S.) (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1995.
Subjects:

MARC

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500 |a Martin, W.J.; Serne, R.J.; Legore, V.L. 
520 3 |a This report describes laboratory experiments performed during 1986-1990 designed to produce empirical leach rate data for cladding removal waste (CRW) grout. At the completion of the laboratory work, funding was not available for report completion, and only now during final grout closeout activities is the report published. The leach rates serve as inputs to computer codes used in assessing the potential risk from the migration of waste species from disposed grout. This report discusses chemical analyses conducted on samples of CRW grout, and the results of geochemical computer code calculations that help identify mechanisms involved in the leaching process. The semi-infinite solid diffusion model was selected as the most representative model for describing leaching of grouts. The use of this model with empirically derived leach constants yields conservative predictions of waste release rates, provided no significant changes occur in the grout leach processes over long time periods. The test methods included three types of leach tests--the American Nuclear Society (ANS) 16.1 intermittent solution exchange test, a static leach test, and a once-through flow column test. The synthetic CRW used in the tests was prepared in five batches using simulated liquid waste spiked with several radionuclides: iodine (¹²⁵I), carbon (¹⁴C), technetium (⁹⁹Tc), cesium (¹³⁷Cs), strontium (⁸⁵Sr), americium (²⁴¹Am), and plutonium (²³⁸Pu). The grout was formed by mixing the simulated liquid waste with dry blend containing Type I and Type II Portland cement, class F fly ash, Indian Red Pottery clay, and calcium hydroxide. The mixture was allowed to set and cure at room temperature in closed containers for at least 46 days before it was tested. 
536 |b AC06-76RL01830. 
650 7 |a Hanford Reservation.  |2 local. 
650 7 |a Radioactive Waste Management.  |2 local. 
650 7 |a Cements.  |2 local. 
650 7 |a Waste Forms.  |2 local. 
650 7 |a Leaching.  |2 local. 
650 7 |a Low-level Radioactive Wastes.  |2 local. 
650 7 |a Radioactive Waste Processing.  |2 local. 
650 7 |a Solidification.  |2 local. 
650 7 |a Grouting.  |2 local. 
650 7 |a Nuclear Fuels.  |2 edbsc. 
710 2 |a Pacific Northwest Laboratory.  |4 res. 
710 2 |a United States.  |b Department of Energy.  |4 spn. 
710 2 |a Pacific Northwest National Laboratory (U.S.).  |4 res. 
710 2 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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