Tritium storage development. Progress report No. 14, October--December 1977. [As a tritide in a metal hydride]

Technical Report · Sat Jan 01 04:00:00 EST 1977

DOI:https://doi.org/10.2172/5044188· OSTI ID:5044188

Colombo, P; Johnson, R

Hydriding studies of zirconium on an engineering scale was continued for application to tritium storage systems. Two runs were made with zirconium sponge in the 297 to 319/sup 0/C temperature range at a hydrogen flow rate of 2.72 cm/sup 3/ at STP/g Zr-min. No significant difference in reaction rate was observed between 99.95 and 99.999 percent minimum purity hydrogen. Seven runs were made with 0.065-in.-thick zirconium sheet at a temperature range of 415 to 526/sup 0/C. Some inconsistency was found in the zirconium sheet reaction data, which is probably the result of differences in buildup of diffusion barrier from specimen to specimen. The reaction with zirconium sheet was found to be more dependent on the degree of outgassing and hydrogen purity, compared with sponge. Maximum reaction rates were 0.080 and 1.34 cm/sup 3/ of H/sub 2/ at STP/cm/sup 2/-min. for 99.95 and 99.999 percent minimum purity hydrogen, respectively.

• Research Organization: Brookhaven National Lab., Upton, N.Y. (USA)
• DOE Contract Number: EY-76-C-02-0016
• OSTI ID: 5044188
• Report Number(s): BNL-50780
• Country of Publication: United States
• Language: English

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12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHEMICAL REACTIONS
ELEMENTS
HYDRIDATION
HYDROGEN ISOTOPES
ISOTOPES
KINETICS
LIGHT NUCLEI
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METALS
NUCLEI
ODD-EVEN NUCLEI
RADIOACTIVE WASTE STORAGE
RADIOISOTOPES
REACTION KINETICS
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TRANSITION ELEMENTS
TRITIUM
WASTE MANAGEMENT
WASTE STORAGE
YEARS LIVING RADIOISOTOPES
ZIRCONIUM