Zirconium hydride as a storage medium for tritium
Conditions necessary for rapid production (approximately 20 minutes preparation time) have been determined for a 6-g sample of zirconium hydride with a composition of ZrH/sub 1.5/ to ZrH/sub 1.9/. Two alternate sets of conditions were found to produce a hydride of suitable physical integrity for tritium storage: the first condition involves isothermal absorption of H/sub 2/ at 760 torr and 600/sup 0/C; the second involves addition of H/sub 2/ at 760 torr as the temperature is increased from 600/sup 0/C until absorption ceases. The latter method appears to produce a hydride which is essentially crack-free. Small amounts of air in the hydrogen were found to have a very deleterious effect on the hydriding reaction. The cost of zirconium is a disadvantage. However, the use of scrap metal may make the method more attractive and the possible use of irradiated Zircaloy cladding hulls would be even more economically favorable. Questions to be answered mainly concern the actinide and other residual activity remaining in the hulls after decladding. Zircaloy-2 tubing, cladding scrap, was studied and found to be very easily hydrided. Hydrides were produced from 0.25- and 0.50-in. diameter Zircaloy rods, 0.50-in. diameter Zircaloy tubing, and a 0.25-in. diameter zirconium rod.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, Wash. (USA)
- DOE Contract Number:
- E(45-1)-1830
- OSTI ID:
- 7143749
- Report Number(s):
- BNWL-2083
- Country of Publication:
- United States
- Language:
- English
Similar Records
Management of waste cladding hulls. Part II. An assessment of zirconium pyrophoricity and recommendations for handling waste hulls
Improving Ductility of Hydride Embrittled Zirconium (Final Report)
Literature Review: Decladding of Zircaloy Clad Light Water Reactor Fuel for the Actinide Recovery Process
Technical Report
·
Mon Oct 31 23:00:00 EST 1977
·
OSTI ID:5203818
Improving Ductility of Hydride Embrittled Zirconium (Final Report)
Technical Report
·
Sat Aug 01 00:00:00 EDT 2020
·
OSTI ID:2203117
Literature Review: Decladding of Zircaloy Clad Light Water Reactor Fuel for the Actinide Recovery Process
Technical Report
·
Fri Jan 31 23:00:00 EST 1992
·
OSTI ID:10197313
Related Subjects
052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHEMICAL REACTIONS
ELEMENTS
HYDRIDATION
HYDRIDES
HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MANAGEMENT
METALS
NUCLEI
ODD-EVEN NUCLEI
RADIOACTIVE WASTE STORAGE
RADIOISOTOPES
STORAGE
TIN ALLOYS
TRANSITION ELEMENT COMPOUNDS
TRANSITION ELEMENTS
TRITIUM
USES
WASTE MANAGEMENT
WASTE STORAGE
YEARS LIVING RADIOISOTOPES
ZIRCALOY
ZIRCONIUM
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
ZIRCONIUM COMPOUNDS
ZIRCONIUM HYDRIDES
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALLOYS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CHEMICAL REACTIONS
ELEMENTS
HYDRIDATION
HYDRIDES
HYDROGEN COMPOUNDS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MANAGEMENT
METALS
NUCLEI
ODD-EVEN NUCLEI
RADIOACTIVE WASTE STORAGE
RADIOISOTOPES
STORAGE
TIN ALLOYS
TRANSITION ELEMENT COMPOUNDS
TRANSITION ELEMENTS
TRITIUM
USES
WASTE MANAGEMENT
WASTE STORAGE
YEARS LIVING RADIOISOTOPES
ZIRCALOY
ZIRCONIUM
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
ZIRCONIUM COMPOUNDS
ZIRCONIUM HYDRIDES