scholarly journals Radioactive Waste Evaporation: Current Methodologies Employed for the Development, Design and Operation of Waste Evaporators at the Savannah River Site and Hanford Waste Treatment Plant

Author(s):  
T. Bond Calloway ◽  
Christopher J. Martino ◽  
Carol M. Jantzen ◽  
William R. Wilmarth ◽  
Michael E. Stone ◽  
...  

Evaporation of High Level and Low Activity (HLW & LAW) radioactive wastes for the purposes of radionuclide separation and volume reduction has been conducted at the Savannah River and Hanford Sites for more than forty years. Additionally, the Savannah River Site (SRS) has used evaporators in preparing HLW for immobilization into a borosilicate glass matrix. The Hanford River Protection Project (RPP) is in the process of building the world’s largest radioactive waste treatment facility, Waste Treatment Plant (WTP), which will use evaporators to concentrate the liquid waste and plant recycles prior to immobilization into a borosilicate glass matrix. Radioactive waste is evaporated at each site using various evaporator designs (e.g., forced circulation, horizontal bent tube). While the equipment used to evaporate radioactive waste is relatively simple in design, the complexity in the evaporator processes in current service and in those currently in the design stages stems from the heterogeneous nature of the waste and the effects of seemingly minor components (e.g., Si) on the process. Aqueous electrolyte thermodynamic modeling and experiments have been conducted by the SRS Savannah River Technology Center (SRTC) in support of the SRS HLW and Defense Waste Processing Facility (DWPF) Evaporators and the Hanford RPP WTP. After 40 years of successful operation, accumulation of two solid phases (a nitrated aluminosilicate, Na8AL6Si6O24(NO3)2•4H2O and sodium diuranate, Na2U2O7) developed as an insoluble phase in the Savannah River Site (SRS) 2H evaporator in 1996. The aluminosilicate scale deposit caused the SRS 2-H evaporator to become completely inoperable by October 1999. Accumulation of the sodium diuranate phase on the aluminosilicate scale has caused criticality concerns. Modeling and experiments were conducted to develop a method to control the process chemistry in order to prevent the formation of aluminosilicate deposits in the future. The lessons learned from the development, design, and operation of the SRS waste treatment facilities and the currently operating 242-A Hanford HLW evaporators were applied by SRTC in support of the development and design of the Hanford WTP evaporators. Thermodynamic equilibrium modeling along with solubility and physical property experiments are being conducted to develop process control and flow sheet models. Additionally, lessons learned from the development of an advanced antifoam agent for the SRS vitrification process evaporators are being applied to the testing and development of an antifoam agent for the Hanford WTP evaporators. This paper will discuss the methodologies, results, and achievements of the SRTC evaporator development program that was conducted in support of the SRS and Hanford WTP evaporator processes. The “cross-pollination” and application of waste treatment technologies and methods between the Savannah River and Hanford Sites will be highlighted. The “cross-pollination” of technologies and methods is expected to benefit the Department of Energy’s Mission Acceleration efforts by reducing the overall cost and time for the development of the baseline waste treatment processes.

Author(s):  
Brigette Rosendall ◽  
Chris Barringer ◽  
Feng Wen ◽  
Kelly J. Knight

The Columbia River in Washington State is threatened by the radioactive legacy of the cold war. Two hundred thousand cubic meters (fifty-three million US gallons) of radioactive waste is stored in 177 underground tanks (60% of the Nation’s radioactive waste). A vast complex of waste treatment facilities is being built to convert this waste into stable glass (vitrification). The waste in these underground tanks is a combination of sludge, slurry, and liquid. The waste will be transported to a pre-treatment facility where it will be processed before vitrification. It is necessary to keep the solids in suspension during processing. The mixing devices selected for this task are known as pulse-jet mixers (PJMs). PJMs cyclically empty and refill with the contents of the vessel to keep it mixed. The transient operation of the PJMs has been proven successful in a number of applications, but needs additional evaluation to be proven effective for the slurries and requirements at the Waste Treatment Plant (WTP). Computational fluid dynamic (CFD) models of mixing vessels have been developed to demonstrate the ability of the PJMs to meet mixing criteria. Experimental studies have been performed to validate these models. These tests show good agreement with the transient multiphase CFD models developed for this engineering challenge.


2005 ◽  
Vol 40 (1-3) ◽  
pp. 297-309 ◽  
Author(s):  
D. D. Walker ◽  
M. A. Norato ◽  
S. G. Campbell ◽  
M. L. Crowder ◽  
S. D. Fink ◽  
...  

Author(s):  
Gheorghe C. Dogaru

Abstract A component of the quality assurance system applied at Radioactive Waste Treatment Plant refers to the collection, identification and characterisation of radioactive waste including spent sealed radioactive sources before their treatment and conditioning. One of the most important challenges to be solved is to apply this procedure to the collection and characterisation of the “historical” radioactive waste for which is not recorded and no analyse bulletin for characterisation and identification is existing. The procedure “Collection and characterization of radioactive waste” applied at the Radioactive Waste Treatment Plant is based on regulatory requirements concerning collection, characterization and identification of all radioactive materials including sealed spent radioactive sources.


1995 ◽  
Vol 27 (2T) ◽  
pp. 104-109
Author(s):  
A. S. Horen ◽  
T. Motyka ◽  
M. J. Montini ◽  
R. F. Hashinger

2009 ◽  
Vol 282 (2) ◽  
pp. 663-667 ◽  
Author(s):  
D. P. DiPrete ◽  
C. C. DiPrete ◽  
N. E. Bibler ◽  
C. J. Bannochie ◽  
M. S. Hay

Author(s):  
Terrel J. Spears ◽  
James W. McCullough ◽  
Harry D. Harmon ◽  
Robert K. Leugemors

The Department of Energy’s (DOE) Savannah River Site (SRS) High-Level Waste (HLW) Program is responsible for storage, treatment, and immobilization of HLW for disposal. The Salt Processing Program (SPP) is the salt (soluble) waste treatment portion of this effort. The overall SPP encompasses the selection, design, construction and operation of treatment technologies to prepare the salt waste feed material for the site’s Saltstone Facility and vitrification facility (Defense Waste Processing Facility). Major constituents that must be removed from the salt waste include actinides, strontium, cesium, and entrained sludge. In fiscal year (FY) 2002, research and development (R&D) on the actinide and strontium removal and Caustic-Side Solvent Extraction (CSSX) processes transitioned from technology development for baseline process selection to providing input for conceptual design of the Salt Waste Processing Facility (SWPF), a key component at the SRS SPP. This work included laboratory studies, bench-scale tests, and prototype equipment development. To implement the salt waste treatment technologies, DOE initiated a competitive procurement process to select Engineering, Procurement, and Construction (EPC) contractors for design of the SWPF. The Department awarded EPC contracts to Parsons Infrastructure & Technology Group, Inc. and Foster Wheeler USA Corporation for preparation of conceptual designs (Phase I) for the SWPF. The two EPC contractors began conceptual design activities in September 2002 and are scheduled to complete this work in January 2004. After evaluation of the conceptual designs, DOE will down select one EPC contractor to continue with final design, construction, and hot commissioning (Phase II). Hot startup of the SWPF is targeted for December 2009.


Sign in / Sign up

Export Citation Format

Share Document