Internal hydrogen embrittlement in uranium alloys

Conference · Tue Dec 22 04:00:00 EST 1981

OSTI ID:5198719

Powell, G L

This paper describes the use of measured hydrogen solubilities and diffusivities to establish methods for heat treating uranium alloys under conditions such that predictable and homogeneous hydrogen contamination is obtained in alloy specimens having well-defined metallurgical histories. From such a series of specimens, correlations are drawn between theoretical hydrogen content and measured properties such as tensile elongation and reduction in area, tensile strength, hydrogen trace analysis, and fracture characteristics. Such correlations are presented for the following alloys: U-0.75Ti, U-2.3Nb, U-6Nb, U-8.5Nb, U-10Nb, U-10Mo, U-7.5Nb-2.5Zr, and unalloyed uranium.

• Research Organization: Oak Ridge Y-12 Plant, TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5198719
• Report Number(s): Y/DU-222; CONF-8105139-1; ON: DE82007003
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105* -- Metals & Alloys-- Corrosion & Erosion
ACTINIDE ALLOYS
ACTINIDES
ALLOYS
ELEMENTS
EMBRITTLEMENT
FRACTURE PROPERTIES
HYDROGEN EMBRITTLEMENT
MATERIALS
MECHANICAL PROPERTIES
METALS
MOLYBDENUM ALLOYS
NIOBIUM ALLOYS
REACTOR MATERIALS
TENSILE PROPERTIES
TITANIUM ALLOYS
URANIUM
URANIUM ALLOYS
URANIUM BASE ALLOYS
ZIRCONIUM ALLOYS