THE TRANSFORMATION BEHAVIOUR OF SOME DILUTE URANIUM ALLOYS
Metallographic and dilatometric studies of the heat treatment behavior of technical uranium and certain alloys of interest for use in natural-uranium fuelled reactors are described. The micro-structure and secondary phases present in high purity and technical purity uranium are first discussed and the time- temperature-transformation data presented. Results on binary alloys comprising U/ Al, U/Cr, U/Fe, U/Mo, U/Nb, U/Ti, U/V, and U/Zr, containing up to about 2 at.% of the alloying element, are described. Cr, Fe, and Zr were found to be the most effective grain refining agents. Al and V were satisfactory under some conditions whereas Mo, Nb, and Ti were ineffective. The grain-size results together with the time-temperaturetransformation curves indicated that grain refinement is associated with depression of the temperature of transformation on heat treatment, the extent of this depression for a given cooling rate being dependent on the alloy content. In practice it was found that alloys such as U/ Zr and U/Fe responded to water quenching treatments, and optimum refinement of others (e.k., U/Cr) resulted from isothermal treatment at 500 to 600 deg C. (auth)
- Research Organization:
- United Kingdom Atomic Energy Authority, Springfields, Lancs, Eng.
- NSA Number:
- NSA-13-006765
- OSTI ID:
- 4283105
- Report Number(s):
- A/CONF.15/P/27
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
STUDY ON THE IMPROVEMENT OF METALLIC URANIUM FUEL. I. THE EFFECTS OF ADDITIVE ELEMENTS, HEAT TREATMENTS AND HOT-ROLLING PROCESS TO THE GRAIN SIZE OF METALLIC URANIUM
AN INVESTIGATION OF TRANSFORMATION CHARACTERISTICS OF THREE URANIUM BASE ALLOYS. Final Report
THE CORROSION BEHAVIOR OF THE NICKEL-CHROMIUM ALLOY INCONEL AND INCONEL AND NIOBIUM ALLOYS IN A PRESSURIZED WATER REACTOR. PART II
Journal Article
·
Thu Feb 28 23:00:00 EST 1963
· Nippon Genshiryoku Gakkaishi (Japan)
·
OSTI ID:4714002
AN INVESTIGATION OF TRANSFORMATION CHARACTERISTICS OF THREE URANIUM BASE ALLOYS. Final Report
Technical Report
·
Mon Dec 31 23:00:00 EST 1962
·
OSTI ID:4708374
THE CORROSION BEHAVIOR OF THE NICKEL-CHROMIUM ALLOY INCONEL AND INCONEL AND NIOBIUM ALLOYS IN A PRESSURIZED WATER REACTOR. PART II
Journal Article
·
Tue May 01 00:00:00 EDT 1962
· Energie nucleaire
·
OSTI ID:4792235