Determination of economic shelf life of spent nuclear fuel
dc.contributor.author | Korcz, Kenneth Walter | en |
dc.contributor.department | Nuclear Science and Engineering | en |
dc.date.accessioned | 2016-02-01T14:45:10Z | en |
dc.date.available | 2016-02-01T14:45:10Z | en |
dc.date.issued | 1977 | en |
dc.description.abstract | The purpose of this study is to determine the constituents of value in spent nuclear fuel and integrate these results into an economic time dependent model of a spent fuel assembly. The value of the constituents in the spent fuel is balanced against the cost of the various nuclear fuel cycle services. BWR and PWR-UO₂/MOX spent fuel assemblies are modeled at 5 different burnups. The recycle modes that are examined are uranium recycle with and without fission product sales and uranium and plutonium recycle with and without fission product sales. UO₂ and MOX spent fuel assemblies discharged from a nuclear reactor from 1977 to 1990 are modeled for a period of 19 years. Four key results of this study are: (1) a re-examination of the value of recycling materials other than uranium and plutonium, namely cesium-137, 134, rhodium, palladium and xenon is justified; (2) the magnitude of the net profits obtainable from the recycling of spent nuclear fuel are tied primarily to burnup and the decision to sell fission products; (3) for fission product recycle, any burnup yields a net positive value with the greater values being at high burnups; and (4) under only spent uranium and plutonium recycle, it is marginally profitable or unprofitable to recycle spent nuclear fuel. The utilization of cesium-137, 134 in the treatment of municipal sludge can reduce the importation of oil by 47.92 million U.S. barrels annually for the United States. | en |
dc.description.degree | Master of Science | en |
dc.format.extent | 346 leaves | en |
dc.format.mimetype | application/pdf | en |
dc.identifier.uri | http://hdl.handle.net/10919/64632 | en |
dc.language.iso | en_US | en |
dc.publisher | Virginia Polytechnic Institute and State University | en |
dc.relation.isformatof | OCLC# 21387172 | en |
dc.rights | In Copyright | en |
dc.rights.uri | http://rightsstatements.org/vocab/InC/1.0/ | en |
dc.subject.lcc | LD5655.V855 1977.K67 | en |
dc.subject.lcsh | Spent reactor fuels | en |
dc.title | Determination of economic shelf life of spent nuclear fuel | en |
dc.type | Thesis | en |
dc.type.dcmitype | Text | en |
thesis.degree.discipline | Nuclear Science and Engineering | en |
thesis.degree.grantor | Virginia Polytechnic Institute and State University | en |
thesis.degree.level | masters | en |
thesis.degree.name | Master of Science | en |
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