PLUTONIUM RECYCLE PROGRAM ANNUAL REPORT, FISCAL YEAR 1960
Four compute codes were developed to investigate reactor physics parameters in terms of over-all fuel cycle economics. Work was continued on the generalized evaluation of self-sustaining plutonium recycle in enriched thermal reactors. Calculations of fuel costs were made for a reactor operating on plutonium recycle without plutonium sale. and for once-through operation and sale of plutonium. The relative wonth of the several plutonium isotopes in a given reactor environment was determined using the Meleager code. Planning and scheduling of basic PRTR fuel loadings were continued to assure maximum contributions of the reactor to the over-all program. Measutements were completed on the fission cross section of Pu/sup 2//sup 4//sup 1/ over the neutron energy region of 0.1 to 20 ev. The subthreshold fission cross sections of U/sup 2//sup 3//sup 4/. U/sup 2//sup 3//sup 6/. U/sup 2//sup 3//sup 8/. and Pa/sup 2//sup 3//sup 1/ were also determined. Critical approach and exponential experiments were conducted with Al--5 wt.% Pu fuel elements in light water to provide critical mass data. Fuel rods for 30 Pu--Al spixe enrichment elements were fabricated. Extensive corrosion testing of various Ru-- Al alloys was performed. Sinterability characteristics, melting curves, thermal expansion, and thermal conductivity of PuO/sub 2/. UO/sub 2/. and mixtures of the two were determined. Hot swaging and vibratory compaction techniques were investigated. Ultrasonic, eddy current, fluorescent dye penetrant, and radiographic tests verified the high metallurgical integrity of the Zircaloy-2 tubes. Evaluation of Zircaloy-4 was carried out to determine its corrosion resistance and hydriding characteristics. Fretting corrosion of Zircaloy-2 components was investigated. Al alloys containing 1 to 2% each of Fe and Ni showed improved corrosion resistance over the more standard X-8001 alloy in 360 deg C water. Preliminary design was completed on the Plutonium Recycle Critical Facility. to be located adjacent to PRTR. Research and development continued on chemical processes for economical separation and decontamination of plutonium and uranium from spent fuels. Work was continued on design of equipment for deconthminating plutonium by ion exchange. (M.C.G.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-15-020324
- OSTI ID:
- 4059767
- Report Number(s):
- HW-67000
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- United States
- Language:
- English
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