Some plutonium recycle program fuel cycles having reduced proliferation characteristics. [BWR; PWR; LMFBR]
E.A. Eschbach
Abstract
E.A. Eschbach
Abstract
A review of the plutonium fuel recycle program (1955-1967) did not reveal an economically compelling alternative fuel cycle to slightly enriched uranium, plutonium recycle, or the plutonium breeder. The review included systems involving no chemical separations compared with slightly enriched uranium once through. Nor did freestanding thorium systems appear economic, although synergisms between uranium and thorium may be worth considering, including reduced-density thorium fuels with high fuel durability as an alternative to uranium load following and peaking fuel. The crossed progeny system involving /sup 233/U enrichment of uranium in light water reactors (LWRs) and conversion of the plutonium to /sup 233/U in fast reactors may offer a method of providing a high-performance denatured LWR fuel for the period beyond the availability of economic slightly enriched uranium.
A significance statement is not available in the OpenAlex record.
A contribution statement is not available in the OpenAlex record.
Method details are not available in the OpenAlex metadata.
Findings are not separately available in the OpenAlex metadata.
Limitations are not available in the OpenAlex metadata.
Application details are not available in the OpenAlex metadata.
A review of the plutonium fuel recycle program (1955-1967) did not reveal an economically compelling alternative fuel cycle to slightly enriched uranium, plutonium recycle, or the plutonium breeder. The review included systems involving no chemical separations compared with slightly enriched uranium once through. Nor did freestanding thorium systems appear economic, although synergisms between uranium and thorium may be worth considering, including reduced-density thorium fuels with high fuel durability as an alternative to uranium load following and peaking fuel. The crossed progeny system involving /sup 233/U enrichment of uranium in light water reactors (LWRs) and conversion of the plutonium to /sup 233/U in fast reactors may offer a method of providing a high-performance denatured LWR fuel for the period beyond the availability of economic slightly enriched uranium.
Key concepts: Plutonium, Uranium, Thorium fuel cycle, MOX fuel, Breeder (animal), Plutonium-240, Thorium, Breeder reactor