RADIATION STABILITY OF FUEL ELEMENTS FOR THE ENRICO FERMI POWER REACTOR

Technical Report · Fri Oct 31 04:00:00 EST 1958

OSTI ID:4306566

Leeser, D O; Rough, F A; Bauer, A A

The irradiation test program on fuel elements for the Enrico Fermi Reactor has covered binary alloys of U-Cr, U-Zr, and U-Mo. The U-5 wt.% Cr eutectic alloy investigation showed insufficient radiation stability for use in a fast reactor being developed as a possible commercially practicable means of producing electric power. Preliminary studies on U- Zr alloys containing 2, 2.2, 3, 5, 10, and 15% by weight of Zr and U-Mo alloys containing 3 1/2, 5, 7, and 10% by weight of Mo have been performed. Various theat treatments were used in preparing the alloyed specimens to determine which treatment, if any, would result in improved radiation stability. A screening program on these binary alloys at low burn-ups (about 0.1 total at.%) indicated that the U-10 wt.% Mo alloy possessed the best stability of the alloys studied, and provided a good reduction of the anisotropic behavior of fabricated U. Therefore, this material was selected as the reference fuel alloys for the Enrico Fermi Reactor. Test data reported include that performed on specimens that were bare, Zr clad with open ends, and Zr clad with ends capped with Zr and with stainless steel. In general, it can be stated that (a) the radiation stability of the gamma treated 10 wt.% material below 1100 deg F is good to 2 at.% burn-up, (b) large changes that occurred, such as swelling or ruptures, have occurred at burn-up less than 10.5 at.% in material irradiated above 1300 deg F, and (c) ruptures occurred in material that is restrained by heavy cladding (8 mil or greater) and/or material that is fabricated improperly. These latter criteria are detailed as to the effects of each and their relative importance to radiation stability. (auth)

• Research Organization: Atomic Power Development Associates, Inc., Detroit; Battelle Memorial Inst., Columbus, Ohio
• NSA Number: NSA-12-014816
• OSTI ID: 4306566
• Report Number(s): A/CONF.15/P/622
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

ANISOTROPY-- BURNUP-- CHROMIUM ALLOYS-- ELECTRICITY-- EUTECTICS-- FUEL ELEMENTS-- HEAT TREATMENTS-- IRRADIATION-- MOLYBDENUM ALLOYS-- POWER-- PRODUCTION-- RADIATIONS-- REACTORS-- SAMPLING-- STABILITY-- TESTING-- URANIUM-- URANIUM ALLOYS-- ZIRCONIUM-- ZIRCONIUM ALLOYS
CANNING-- FAILURES-- HIGH TEMPERATURE-- STAINLESS STEELS-- TEMPERATURE
MINERALOGY, METALLURGY, AND CERAMICS