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Title: REACTOR GROUT THERMAL PROPERTIES

Savannah River Site has five dormant nuclear production reactors. Long term disposition will require filling some reactor buildings with grout up to ground level. Portland cement based grout will be used to fill the buildings with the exception of some reactor tanks. Some reactor tanks contain significant quantities of aluminum which could react with Portland cement based grout to form hydrogen. Hydrogen production is a safety concern and gas generation could also compromise the structural integrity of the grout pour. Therefore, it was necessary to develop a non-Portland cement grout to fill reactors that contain significant quantities of aluminum. Grouts generate heat when they set, so the potential exists for large temperature increases in a large pour, which could compromise the integrity of the pour. The primary purpose of the testing reported here was to measure heat of hydration, specific heat, thermal conductivity and density of various reactor grouts under consideration so that these properties could be used to model transient heat transfer for different pouring strategies. A secondary purpose was to make qualitative judgments of grout pourability and hardened strength. Some reactor grout formulations were unacceptable because they generated too much heat, or started setting too fast, or requiredmore » too long to harden or were too weak. The formulation called 102H had the best combination of characteristics. It is a Calcium Alumino-Sulfate grout that contains Ciment Fondu (calcium aluminate cement), Plaster of Paris (calcium sulfate hemihydrate), sand, Class F fly ash, boric acid and small quantities of additives. This composition afforded about ten hours of working time. Heat release began at 12 hours and was complete by 24 hours. The adiabatic temperature rise was 54 C which was within specification. The final product was hard and displayed no visible segregation. The density and maximum particle size were within specification.« less
Authors:
; ; ;
Publication Date:
OSTI Identifier:
1012544
Report Number(s):
SRNL-STI-2010-00806
TRN: US201110%%243
DOE Contract Number:
DE-AC09-08SR22470
Resource Type:
Technical Report
Research Org:
SRS
Sponsoring Org:
DOE
Country of Publication:
United States
Language:
English
Subject:
08 HYDROGEN; BORIC ACID; CALCIUM; CEMENTS; FLY ASH; GROUND LEVEL; GROUTING; GYPSUM CEMENTS; HEAT TRANSFER; HYDRATION; HYDROGEN; HYDROGEN PRODUCTION; PARTICLE SIZE; PORTLAND CEMENT; PRODUCTION REACTORS; SPECIFIC HEAT; SULFATES; TANKS; THERMAL CONDUCTIVITY; THERMODYNAMIC PROPERTIES