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Title: COMPATIBILITY OF ZIRCONIUM HYDRIDE AND CARBON DIOXIDE

Abstract

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)

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

Citation Formats

Shoemaker, H E. COMPATIBILITY OF ZIRCONIUM HYDRIDE AND CARBON DIOXIDE. United States: N. p., 1959. Web. doi:10.2172/4210987.
Shoemaker, H E. COMPATIBILITY OF ZIRCONIUM HYDRIDE AND CARBON DIOXIDE. United States. https://doi.org/10.2172/4210987
Shoemaker, H E. 1959. "COMPATIBILITY OF ZIRCONIUM HYDRIDE AND CARBON DIOXIDE". United States. https://doi.org/10.2172/4210987. https://www.osti.gov/servlets/purl/4210987.
@article{osti_4210987,
title = {COMPATIBILITY OF ZIRCONIUM HYDRIDE AND CARBON DIOXIDE},
author = {Shoemaker, H E},
abstractNote = {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)},
doi = {10.2172/4210987},
url = {https://www.osti.gov/biblio/4210987}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1959},
month = {7}
}