BLENDED CALCIUM ALUMINATE-CALCIUM SULFATE CEMENT-BASED GROUT FOR P-REACTOR VESSEL IN-SITU DECOMMISSIONING [electronic resource]
The objective of this report is to document laboratory testing of blended calcium aluminate - calcium hemihydrate grouts for P-Reactor vessel in-situ decommissioning. Blended calcium aluminate - calcium hemihydrate cement-based grout was identified as candidate material for filling (physically stabi...
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Online Access |
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| 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,
2011.
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| Subjects: |
MARC
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| 245 | 0 | 0 | |a BLENDED CALCIUM ALUMINATE-CALCIUM SULFATE CEMENT-BASED GROUT FOR P-REACTOR VESSEL IN-SITU DECOMMISSIONING |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 2011. | ||
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| 500 | |a Published through the Information Bridge: DOE Scientific and Technical Information. | ||
| 500 | |a 03/10/2011. | ||
| 500 | |a "srnl-sti-2010-00427" | ||
| 500 | |a Langton, C.; Stefanko, D. | ||
| 520 | 3 | |a The objective of this report is to document laboratory testing of blended calcium aluminate - calcium hemihydrate grouts for P-Reactor vessel in-situ decommissioning. Blended calcium aluminate - calcium hemihydrate cement-based grout was identified as candidate material for filling (physically stabilizing) the 105-P Reactor vessel (RV) because it is less alkaline than portland cement-based grout which has a pH greater than 12.4. In addition, blended calcium aluminate - calcium hemihydrate cement compositions can be formulated such that the primary cementitious phase is a stable crystalline material. A less alkaline material (pH {<=} 10.5) was desired to address a potential materials compatibility issue caused by corrosion of aluminum metal in highly alkaline environments such as that encountered in portland cement grouts [Wiersma, 2009a and b, Wiersma, 2010, and Serrato and Langton, 2010]. Information concerning access points into the P-Reactor vessel and amount of aluminum metal in the vessel is provided elsewhere [Griffin, 2010, Stefanko, 2009 and Wiersma, 2009 and 2010, Bobbitt, 2010, respectively]. Radiolysis calculations are also provided in a separate document [Reyes-Jimenez, 2010] | |
| 536 | |b DE-AC09-08SR22470. | ||
| 650 | 7 | |a Aluminates. |2 local. | |
| 650 | 7 | |a Corrosion. |2 local. | |
| 650 | 7 | |a Calcium. |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 Sulfates. |2 local. | |
| 650 | 7 | |a Radiolysis. |2 local. | |
| 650 | 7 | |a Testing. |2 local. | |
| 650 | 7 | |a Compatibility. |2 local. | |
| 650 | 7 | |a Aluminium. |2 local. | |
| 650 | 7 | |a Cements. |2 local. | |
| 650 | 7 | |a General Studies Of Nuclear Reactors. |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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