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Title: ORNL isotopic power fuels quarterly report for period ending March 31, 1969

Technical Report ·
OSTI ID:4406180

Declassified 29 Mar 1973. A Thermionic Engineering Mockup test was scheduled. The heat source matrix and the test capsule designs for this mockup were completed. A new method for measuring the heat capacity of selfheated radioactive materials was devised. The shipment of /sup 244/Cm from Savannah River Laboratory was assayed calorimetrically; the values obtained are in good agreement with those reported by Savannah River. A transverse cracking problem developed during the production of welded TZM creep specimens. This cold cracking'' appears to be initiated by hot cracking.'' Welding conditions have been optimized for the metals and alloys to be investigated in the low- and intermediate-temperature tests. Chemical analyses of the compatibility couples of Hastelloy C with nonradioactive SrTiO/sub 3/ containing 1% SiO/sub 2/ additive showed a pickup of oxygen at 1100 deg C. Experiments showed that the most likely impurity which could provide the oxygen is water. Studies were begun to determine the effect of the decay products on /sup 90/Sr fuels. The creep rates of Haynes 25 specimens in vacuum at 90O deg C are ~40 times greater than those tested in air and their rupture lives are ~25 times lower. The third SNAP-21 generator was loaded and shipped to 3M Company. Preparations are being made to hydrostatically test the SNAP-23 capsules. (auth)

Research Organization:
Oak Ridge National Lab., Tenn. (USA)
DOE Contract Number:
W-7405-ENG-26
NSA Number:
NSA-29-002813
OSTI ID:
4406180
Report Number(s):
ORNL-4432
Resource Relation:
Other Information: Declassified 29 Mar 1973. Orig. Receipt Date: 30-JUN-74
Country of Publication:
United States
Language:
English