Tritium storage development. Progress report No. 12, April--June 1977. [In metal hydride; polymer impregnated tritiated concrete]
Laboratory work was continued on hydriding of zirconium sponge and rod under varying conditions of temperature (400 to 900/sup 0/C) and pressure (0-1000 torr) to determine optimum conditions for the formation of hydrides with desirable mechanical properties. Titanium sponge and rod were also hydrided for comparison. Zirconium and titanium samples containing tritium were prepared and initial leach data were obtained. Leach rates for zirconium in distilled water ranged from 1.1 x 10/sup -6/ to 4.8 x 10/sup -6/ cm/day under static conditions and from 2.1 x 10/sup -6/ to 1.1 x 10/sup -5/ cm/day under dynamic conditions. The leach rates for titanium sponge and rod under static conditions ranged from 2.2 x 10/sup -7/ to 1.7 x 10/sup -6/ cm/day. Construction of the engineering scale equipment has been completed and testing has been started prior to operation. Lysimeter testing of polymer impregnated tritiated concrete (PITC) specimens has continued. After sixty-two weeks, the average of the four test specimens indicates a a linear rate of release with a slope of 5.23 x 10/sup -2/ cm/yr. beginning after 250 days. A duplicate PITC static leach specimen in distilled water after 386 days indicates a linear rate of release with a slope of 3.18 x 10/sup -2/ cm/yr. Developmental work is continuing on the injector technique for PITC. Nontritiated prototype specimens, as well as tritiated specimens for static leach testing in distilled water, were prepared. (20 figures, 9 tables)
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- EY-76-C-02-0016
- OSTI ID:
- 5201883
- Report Number(s):
- BNL-50733
- Country of Publication:
- United States
- Language:
- English
Similar Records
Tritium storage development. Progress report No. 13, July--September 1977
Tritium storage development. Progress report No. 7, January--March 1976. [Polymer impregnated tritiated concrete]
Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CHEMICAL REACTIONS
CONCRETES
DISSOLUTION
ELEMENTS
HYDRIDATION
HYDRIDES
HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
IMPREGNATION
ISOTOPES
LABELLED COMPOUNDS
LEACHING
LIGHT NUCLEI
MANAGEMENT
MATERIALS
METALS
NUCLEI
ODD-EVEN NUCLEI
POLYMERS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE DISPOSAL
RADIOISOTOPES
RESEARCH PROGRAMS
SEPARATION PROCESSES
STORAGE
TITANIUM
TITANIUM COMPOUNDS
TITANIUM HYDRIDES
TRANSITION ELEMENT COMPOUNDS
TRANSITION ELEMENTS
TRITIUM
TRITIUM COMPOUNDS
WASTE DISPOSAL
WASTE MANAGEMENT
YEARS LIVING RADIOISOTOPES
ZIRCONIUM
ZIRCONIUM COMPOUNDS
ZIRCONIUM HYDRIDES