COMPATIBILITY OF ZIRCONIUM HYDRIDE AND CARBON DIOXIDE

Technical Report · Wed Jul 01 00:00:00 EDT 1959

DOI:https://doi.org/10.2172/4210987· OSTI ID:4210987

Shoemaker, H E

The stability of unclad zirconium hydride was investigated as a reactor moderator in carbon dioxide coolant. Two ranges of hydride were tested, an alpha- plus deltaphase hydride (ZrH/sub 0.9 plus or minus 0.2/) and a delta-phase hydride (ZrH/sub 1.5/). The delta-phase hydride exhibited excellent dimensional stability, but suffered as great as 20% hydrogen loss at 1200 deg F, together with severe corrosion. The alphaplus delta-phase hydride swelled and warped in a temperature gradient but did not lose much hydrogen and did not corrode severely even at 1200 deg F. The results indicate that zirconium hydride could not be used as unclad moderator in a carbon dioxide atmosphere in the temperature range desired for the Maritime Gas Cooled Reactor. (auth)

• Research Organization: General Atomic Dev., General Dynamics Corp., San Diego, Calif.
• Sponsoring Organization: USDOE
• DOE Contract Number: AT(04-3)-187
• NSA Number: NSA-14-009772
• OSTI ID: 4210987
• Report Number(s): GA-849
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-60
• Country of Publication: United States
• Language: English

Related Subjects

METALS, CERAMICS, AND MATERIALS
CANNING
CARBON DIOXIDE
COOLANTS
CORROSION
GAS COOLANT
HIGH TEMPERATURE
HYDROGEN
LOSSES
MATERIALS TESTING
MGCR
MODERATORS
PHASE DIAGRAMS
REACTORS
STABILITY
TEMPERATURE
ZIRCONIUM HYDRIDES