ORNL isotopic power fuels quarterly report for period ending September 30, 1973
Heat soak periods were completed on four of the ten sets of compatibility couples which were put on test during the previous quarter. The four sets contain a total of 18 couples. Four couples were examined, and tests on the others are in progress. Examination of the Kilowatt Test Source capsule was completed. Four Cm/sup 203/ceramic couples were examined and additional tests are underway. Materials selection and test conditions were finalized for a 15-couple matrix to be initinted during FY 1974. Free energy calculations were made for the reactions of Cm/sub 2/O/sub 3/ with Pt-26% Rh- 8% W, T- 111, Hafnalloy 20-20, stainless steel type 316, Ir-2% W, Pt-30% Rh- 8% W, and carbon. The cquipment assemblies for the helium release, emissivity, vapor pressure, and heat capacity experiments were completed and checked out. A comparison of physical stability was made between two essentially identical Cm/sub 2/O/sub 3/ pellets, one stored in dry air and one stored in argon. Some degradation of the air-stored pellet was noted but there was no observable change in the pellet stored in argon. Measurements of rnte-of-loss of /sup 244/Cm from s of conditions-fresh air-saturated flowing seawater at ambient temperature and a fixed volume of boiling seawater. The rate of weight gain in dry air was measured for a hot-pressed Cm/sub 2/O/sub 3/ pellet of relatively low density. Calculation weight loss measurements and dry air weight gain measurements were made on a fraction of purified curium oxide. Neutron radiation dnta from the / sup the 244/Cm source measurement made last quarter were analyzed and compared to literature values. The source was re-analyzed by calorimetry, and the /sup 244/ Cm content as of date of the radiation measurement was calculated. The equipment for the Cm/sub 2/O/sub 3/ apart study was stored due to a postponement of this project. Analytical work on the /sup 244/Cm product which is currently being used for characterization tests was completed. Two fractions of stored /sup 244/ Cm residues were processed at the TRU facility and yielded 77 g of highly pure curium oxide for test work. Calculations of the yield of /sup 244/Cm as a function of /sup 235/U enrichment in PWR operations were made. The variation in isotopic abundances of the four principal curium isotopes were calculated for five reference reactors. (auth)
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-29-010327
- OSTI ID:
- 4410611
- Report Number(s):
- ORNL-4932
- Resource Relation:
- Other Information: 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, 1967
NUCLEAR STUDY OF CONTROL POISONS FOR S3G/S4G
Related Subjects
*CURIUM 244- RADIOISOTOPE HEAT SOURCES
*RADIOISOTOPE HEAT SOURCES- RESEARCH PROGRAMS
*THERMOELECTRIC GENERATORS- RADIOISOTOPE HEAT SOURCES
CARBON
COMPATIBILITY
CURIUM OXIDES
FABRICATION
HAFNIUM BASE ALLOYS- PALLADIUM ALLOYS- PLATINUM ALLOYS- TIN ALLOYS
IMPACT STRENGTH
IRIDIUM BASE ALLOYS- TUNGSTEN ALLOYS
ISOTOPE PRODUCTION
PLATINUM BASE ALLOYS- RHODIUM ALLOYS- TUNGSTEN ALLOYS
SPECIFIC HEAT
STAINLESS STEEL-316
TANTALUM ALLOY-T111
VAPOR PRESSURE PLATINUM BASE ALLOYS- RHODIUM ALLOYS- TUNGSTEN ALLOYS
NESDPS Office of Nuclear Energy Space and Defense Power Systems