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WIPP: Lessons in transportation safety
As part of a future consent-based approach by the federal government to site new deep geologic repositories for nuclear waste, local communities and states that are considering hosting such facilities are sure to have many questions. Currently, the Waste Isolation Pilot Plant in New Mexico is the only example of such a repository in operation, and it offers the opportunity for state and local officials to visit and judge for themselves the risks and benefits of hosting a similar facility. But its history can also provide lessons for these officials, particularly the political process leading up to the opening of WIPP, the safety of WIPP operations and transportation of waste from generator facilities to the site, and the economic impacts the project has had on the local area of Carlsbad, as well as the rest of the state of New Mexico.
Louis J. Barbieri, J. Wallace Webster, Ken Tang Chow
Nuclear Science and Engineering | Volume 5 | Number 2 | February 1959 | Pages 105-119
Technical Paper | doi.org/10.13182/NSE59-A25563
Articles are hosted by Taylor and Francis Online.
The economics and physics of plutonium recycle in the Calder Hall type reactor are considered. Three possible schemes of recycle are studied. In scheme A the plutonium produced in a run is blended with fresh natural uranium for a subsequent run; in scheme B the plutonium is alloyed with some diluent metal and fabricated into high heat-transfer elements more like MTR- or PWR-seed type elements and a subsequent load of fresh natural uranium elements is “spiked” with these plutonium elements; and in scheme C half the spent uranium is recycled as well as the plutonium. The conclusions are that scheme A will be the most economic means of recycle and will compete very favorably with the mode of operation where the plutonium is sold at the end of each run for $12 per gm. Viewed in another way, with natural uranium having its current value and lease charge, the fuel value of plutonium for recycling, with all costs considered, will be greater than $12 per gm. Schemes B and C do not look as attractive as A for the Calder Hall type reactor. The results are predicated on the assumption that the fuel elements will withstand exposure levels as high as 8800 Mwd/ton. This is beyond present experience, but it is believed that it is not unrealistic to assume that such exposures will be achieved in the future with improved fuel elements. A matrix-analytic solution to the differential equations governing isotopic concentrations as functions of flux-time is also developed.