ORNL isotopic power fuels quarterly report for period ending September 30, 1967
Declassified 29 Mar 1973. Experiments were designed to determine the helium release from three types of /sup 244/Cm/sub 2/O/sub 3/ fuel forms. A program was initiat ed to determine the compatibility of /sup 244/Cm/sub 2/O/sub 2/ with Ta, Ta--10% W, T-111, Mo, TZM, W, and W--26% Re at temperatures of 1650 and 1850 deg C. Experiments were designed to obtain characteristics (i.e., creep strength, thermal conductivity) of potential containment materials in their operating environments. A thermionic capsule support system was conceptually designed. Studies were initfated to determine the applicability of the sol-gel process to the preparation of curium oxide spheres. The use of the modified thermal conductivity apparatus (3M Model TC-200) was successfully demonstrated using an electrically heated pellet to simulate /sup 90/Sr fuel forms. A program was initiated to evaluate the compatibility of SrO, SrTiO/sub 3/, and Sr/sub 2/ TiO/sub 4/ with Hastelloy C, Haynes 25 , and Type 316 stainless steel. A 32,000- curie SrO source clad in platinum that had been exposed to a temperature of 780 deg C for 90 days was examined; the source was contained in an inner capsule of Hastelloy X and an outer capsule of Hastelloy C. A hot press for pressing 4-in.- dia SrTiO/sub 3/ pellets was designed. Examination of the effect of weld current variation on penetration for several joint designs and the optinnunn penetration which could be obtained with a given joint design while retaining one edge for ultrasonic testing purposes was begun. The oxidation resistance of capsule materials (Hastelloy C, Inconel 600, and platinum) in air at 2000 deg F and the corrosion resistance at 2000 deg F in clay-type soil common in the vicinity of ORNL were obtained for periods up to 6 and 7 months, respectively. Microspheres of /sup 238/PuO/sub 2/ with a density high enough to meet necessary requirements were prepared by the modified sol-gel process for the small-scale experimental program. The 24 pellets contained in the four capsules of the SNAP-7A generator were removed and inspected; 15 were completely intact, 7 were cracked, 1 was chipped, and 1 was broken into several pieces. There was no visible evidence of mechanical damage or chemical attack on the Inside capsule surfaces or spacers. The proposed requirements of the SNAP-21 capsule weld acceptance criteria were prepared. A device for handling the loaded SNAP-23A capsule liner and placing the capsule in the welding chamber was designed. Aging conditions and results of Charpy impact tests at 600 deg F on Haynes 25 were obtained. (auth)
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-29-002812
- OSTI ID:
- 4423411
- Report Number(s):
- ORNL-4205
- Resource Relation:
- Other Information: Declassified 29 Mar 1973. Orig. Receipt Date: 30-JUN-74
- Country of Publication:
- United States
- Language:
- English
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ORNL isotopic power fuels quarterly report for period ending September 30, 1969
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Related Subjects
*CAPSULES- OXIDATION
*CURIUM 244- RADIOISOTOPE HEAT SOURCES
*CURIUM OXIDES- COMPATIBILITY
*PLUTONIUM 238- RADIOISOTOPE HEAT SOURCES
*RADIOISOTOPE HEAT SOURCES- RESEARCH PROGRAMS
*STRONTIUM 90- RADIOISOTOPE HEAT SOURCES
*STRONTIUM OXIDES- COMPATIBILITY
CORROSION
HASTELLOY C
HASTELLOY X
HAYNES 25 ALLOY
IMPACT TESTS
INCONEL 600
PLATINUM
SNAP 21 BATTERY
SNAP 7 BATTERY
STAINLESS STEEL-316
TEMPERATURE DEPENDENCE
NESDPS Office of Nuclear Energy Space and Defense Power Systems