scholarly journals Technical Bases for the Dwpf Testing Program

1990 ◽  
Vol 212 ◽  
Author(s):  
M. J. Plodinec

ABSTRACTThe Defense Waste Prsocessing Facility (DWPF) at the Savannah River Site (SRS) will be the first production facility in the United States for the immobilization of high-level nuclear waste. Production of DWPF canistered wasteforms will begin prior to repository licensing, so decisions on facility startup will have to be made before the final decisions on repository design are made. The Department of Energy’s Office of Civilian Radioactive Waste Management (RW) has addressed this discrepancy by defining a Waste Acceptance Process. This process provides assurance that the borosilicate-glass wasteform, in a stainless-steel canister, produced by the DWPF will be acceptable for permanent storage in a federal repository. As part of this process, detailed technical specifications have been developed for the DWPF product.SRS has developed detailed strategies for demonstrating compliance with each of the Waste Acceptance Process specifications. An important part of the compliance is the testing which will be carried out in the DWPF. In this paper, the bases for each of the tests to be performed in the DWPF to establish compliance with the specifications are described, and the tests are detailed. The results of initial tests relating to characterization of sealed canisters are reported.

Author(s):  
D. T. Hobbs ◽  
T. B. Peters ◽  
M. C. Duff ◽  
M. J. Barnes ◽  
S. D. Fink ◽  
...  

A significant fraction of the high-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) must be pretreated to remove 137Cs, 90Sr and alpha-emitting radionuclides (i.e., actinides) prior to disposal onsite as low level waste. Separation processes planned at the SRS include caustic side solvent extraction for 137Cs and sorption onto monosodium titanate (MST) for 90Sr and alpha-emitters. The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes 238Pu, 239Pu and 240Pu. This paper describes the planned Sr/actinide separation process and summarizes recent tests and demonstrations with simulated and actual tank waste solutions.


2001 ◽  
Vol 7 (S2) ◽  
pp. 498-499
Author(s):  
J. S. Young ◽  
Y. Su ◽  
L. Li ◽  
M. L. Balmer

Millions of gallons of high-level radioactive waste are contained in underground tanks at U. S. Department of Energy sites such as Hanford and Savannah River. Most of the radioactivity is due to 137Cs and 90Sr, which must be extracted in order to concentrate the waste. An ion exchanger, crystalline silicotitanate IONSIV® IE911, is being considered for separation of Cs at the Savannah River Site (SRS). While the performance of this ion exchanger has been well characterized under normal operating conditions, Cs removal at slightly elevated temperatures, such as those that may occur in a process upset, is not clear. Our recent study indicates that during exposure to SRS simulant at 55°C and 80°C, an aluminosilicate coating formed on the exchanger surface. There was concern that the coating would affect its ion exchange properties. A LEO 982 field emission scanning electron microscope (FESEM) and an Oxford ISIS energy dispersive x-ray spectrometer (EDS) were used to characterize the coating.


2008 ◽  
Vol 97 (1-2) ◽  
pp. 75-86 ◽  
Author(s):  
Wenqian Dou ◽  
Kamel Omran ◽  
Stefan J. Grimberg ◽  
Miles Denham ◽  
Susan E. Powers

Sign in / Sign up

Export Citation Format

Share Document