An International Spent Nuclear Fuel Storage Facility: by Glenn E. Schweitzer and A. Chelsea Sharber, Editors

By Glenn E. Schweitzer and A. Chelsea Sharber, Editors

As a part of a long-standing collaboration on nuclear nonproliferation, the nationwide Academy of Sciences and the Russian Academy of Sciences held a joint workshop in Moscow in 2003 at the medical features of a world radioactive disposal web site in Russia. The passage of Russian legislation allowing the importation and garage of high-level radioactive fabric (primarily spent nuclear gas from reactors) has engendered curiosity from a few international governments, together with the united states, in exploring the potential for moving fabric to Russia on a short lived or everlasting foundation. The workshop interested in the environmental features of the final place and features of a potential garage website, transportation to and in the website, packing containers for transportation and garage, stock and responsibility, audits and inspections, and dealing with applied sciences.

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Additional info for An International Spent Nuclear Fuel Storage Facility: Exploring a Russian Site As a Prototype

Sample text

The statutory limit for Yucca Mountain is 63,000 tons, and the United States should reach that limit by the year 2015. After 2015 either Yucca Mountain will have to be expanded greatly or a new repository will have to be constructed. If transmutation and uranium separation prove implementable on a commercial scale, the quantity of waste sent to the repository could be stabilized at a level that would eliminate the need for a significant expansion of Yucca Mountain or even a second repository. The significant cost benefits derived from reprocessing the spent fuel going into Yucca Mountain are shown in the DOE estimates in Table 3.

Development of Separations Technologies Under the Advanced Fuel Cycle Initiative. Report to the ANTT Subcommittee. December 2002. Phase II: Proof of Principle Under Phase II of the AFCI Program, which is considered the proof-ofprinciple phase, the following activities will be pursued: • The most promising technologies from Phase I, such as UREX/UREX+, will be identified for focused research and development. While many experts believe that UREX/UREX+ can be implemented on a commercial scale, dry processes like pyroprocessing may have advantages in handling large concentrations of transuranics.

As a result, only spent fuel not subject to reprocessing was included within the scope of the convention. As for the position of each country on the matter of spent fuel and radioactive waste management, the parties to the convention recognize, first, that setting policy regarding the nuclear fuel cycle remains the prerogative of each individual state and, second, that some states consider spent fuel a valuable resource that can be reprocessed, while others prefer to bury it. The convention also notes that radioactive wastes must be buried in the country in which they were produced, recognizing that in certain circumstances the safety of spent fuel and radioactive waste management could be enhanced by an agreement among the parties regarding the use of the facilities of one country in the interests of other countries.

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