PRELIMINARY IRRADIATIONS OF PuC AND UC-PuC
Conference
·
OSTI ID:4767563
The C content of the specimens used in the irradiations ranged from 4.75to 5.73%. The Pu content of the mixed carbide specimens was varied from 17.2 to 27.8%. Results are presented of tests in which PuC and mixed carbide specimens were irradiated to burnups ranging from 500 to 770 Mwd/mt at central temperatures ranging from 370 to 850 deg C. Pressed and sintered pellets of mixed carbide were irradiated to burnups ranging from 54 to 810 Mwd/mt and central fuel temperatures at 260 to 380 deg C. (J.R.D.)
- Research Organization:
- Argonne National Lab., Ill.; Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- DOE Contract Number:
- W-31109-ENG-38
- NSA Number:
- NSA-17-012711
- OSTI ID:
- 4767563
- Report Number(s):
- ANL-FGF-399; UAC-7022
- Country of Publication:
- United States
- Language:
- English
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