ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING GROUTING OPERATIONS IN THE R AND P REACTOR VESSELS [electronic resource]

The R- and P-reactor buildings were retired from service and are now being prepared for deactivation and decommissioning (D&D). D&D activities will consist primarily of immobilizing contaminated components and structures in a grout-like formulation. Aluminum corrodes very rapidly when it com...

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Bibliographic Details
Online Access: Online Access
Corporate Author: United States. Department of Energy. Savannah River Site (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, 2009.
Subjects:

MARC

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245 0 0 |a ASSESSMENT OF THE POTENTIAL FOR HYDROGEN GENERATION DURING GROUTING OPERATIONS IN THE R AND P REACTOR VESSELS  |h [electronic resource] 
260 |a Washington, D.C. :  |b United States. Dept. of Energy ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,  |c 2009. 
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500 |a Published through the Information Bridge: DOE Scientific and Technical Information. 
500 |a 10/29/2009. 
500 |a "srnl-sti-2009-00639" 
500 |a Wiersma, B. 
520 3 |a The R- and P-reactor buildings were retired from service and are now being prepared for deactivation and decommissioning (D&D). D&D activities will consist primarily of immobilizing contaminated components and structures in a grout-like formulation. Aluminum corrodes very rapidly when it comes in contact with the alkaline grout materials and as a result produces hydrogen gas. To address this potential deflagration/explosion hazard, the Materials Science and Technology Directorate (MS&T) of the Savannah River National Laboratory (SRNL) has been requested to review and evaluate existing experimental and analytical studies of this issue to determine if any process constraints on the chemistry of the fill material and the fill operation are necessary. Various options exist for the type of grout material that may be used for D&D of the reactor vessels. The grout formulation options include ceramicrete (pH 6-8), low pH portland cement + silica fume grout (pH 10.4), or portland cement grout (pH 12.5). The assessment concluded that either ceramicrete or the silica fume grout may be used to safely grout the R- and P- reactor vessels. The risk of accumulation of a flammable mixture of hydrogen between the grout-air interface and the top of the reactor is very low. Conservative calculations estimate that either ceramicrete or the silica fume grout may be used to safely grout the R- and P- reactor vessels. The risk of accumulation of a flammable mixture of hydrogen between the grout-air interface and the top of the reactor is very low. Although these calculations are conservative, there are some measures that may be taken to further minimize the potential for hydrogen evolution. (1) Minimize the temperature of the grout as much as practical. Lower temperatures will mean lower hydrogen generation rates. Grout temperatures less than 100 C should however, still provide an adequate safety margin for the pH 8 and pH 10.4 grout formulations. (2) Minimize the fill rate as much as practical. Lowering the fill rate takes advantage of passivation of the aluminum components and hence lower hydrogen generation rates. Fill rates that are less than 2 inches/min will reduce the chance of significant hydrogen build-up. (3) Ventilate the building as much as practical (e.g., leave doors open) to further disperse hydrogen. The volumetric hydrogen generation rates however, are low for the pH 8 and pH 10.4 grout, i.e., less than 0.32 ft³/min. Portland cement grout, on the other hand, for the same range of process parameters does not provide a significant margin of safety against the accumulation of flammable gas in the reactor vessel during grouting operations. It is recommended that this grout not be utilized for this task. If further walk-down inspections of the reactor vessels suggest an increase in the actual areal density of aluminum, the calculations should be re-visited. 
536 |b DE-AC09-08SR22470. 
650 7 |a Silica.  |2 local. 
650 7 |a Safety.  |2 local. 
650 7 |a Deactivation.  |2 local. 
650 7 |a Grouting.  |2 local. 
650 7 |a P Reactor.  |2 local. 
650 7 |a Reactor Vessels.  |2 local. 
650 7 |a Decommissioning.  |2 local. 
650 7 |a Portland Cement.  |2 local. 
650 7 |a Mixtures.  |2 local. 
650 7 |a Chemistry.  |2 local. 
650 7 |a Passivation.  |2 local. 
650 7 |a Hydrogen.  |2 local. 
650 7 |a Safety Margins.  |2 local. 
650 7 |a Aluminium.  |2 local. 
650 7 |a Materials Science.  |2 edbsc. 
650 7 |a Hydrogen.  |2 edbsc. 
710 1 |a United States.  |b Department of Energy.  |b Savannah River Site.  |4 res. 
710 1 |a United States.  |b Department of Energy.  |4 spn. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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