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 clinical points of a world radioactive disposal website 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 overseas governments, together with the united states, in exploring the potential of moving fabric to Russia on a brief or everlasting foundation. The workshop desirous about the environmental facets of the overall situation and features of a potential garage website, transportation to and in the web site, bins 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
The significant cost benefits derived from reprocessing the spent fuel going into Yucca Mountain are shown in the DOE estimates in Table 3. 0E + + + + + + + + + + + + + + + + + + + + + 02 02 03 07 06 07 04 07 05 07 07 07 07 06 04 02 04 03 05 04 05 SOURCE: James Laidler. Development of Separations Technologies Under the Advanced Fuel Cycle Initiative. Report to the ANTT Subcommittee. December 2002. would not be needed. With no reprocessing, a second repository is estimated to cost $35 billion. The total savings for disposal from separation of uranium and transmutation is estimated at about $53 billion.
5 m 3/y) Denitration FIGURE 6 UREX+ process flowsheet. (Storage volumes based on 2000 tons spent nuclear fuel per year, 10-year cooling; 2210 m3 per year if disposed directly in a geologic repository). SOURCE: James Laidler. Development of Separations Technologies Under the Advanced Fuel Cycle Initiative. Report to the ANTT Subcommittee. December 2002. 5% recovery (recycle) RAFFINATE Am, Cm, FP Aqueous phase Organic phase FIGURE 7 Pu/Np extraction flowsheet. SOURCE: James Laidler. Development of Separations Technologies Under the Advanced Fuel Cycle Initiative.
III-2. S. S. secretary of energy on issues pertaining to civilian nuclear energy, science, and technology. In 1999 NERAC established the ATW Subcommittee to provide advice on the accelerator transmutation of high-level waste from civilian nuclear reactors. Accelerator-induced transmutation has a unique set of problems, such as accelerator reliability and the uncertain problems of coupling an accelerator to the remaining transmutation complex. Given the formidable time and expense to develop this accelerator-based technology, and given the ability of fast reactors (such as those already contemplated for the next generation of nuclear reactors called GEN-IV) to do the same job, the subcommittee early in its deliberations decided to change its name to the Advanced Nuclear Transformation Technology (ANTT) Subcommittee and recommended that DOE not emphasize the use of accelerators for transmutation but place more emphasis on the use of fast reactors.