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Virginia Polytechnic Institute and State University

Determination of economic shelf life of spent nuclear fuel

Abstract

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.

Degree

thesis:*
Name thesis:degree_name
Master of Science
Level thesis:degree_level
masters
Discipline thesis:degree_discipline
Nuclear Science and Engineering
Department dc:contributor.department
Nuclear Science and Engineering
Grantor dc:publisher
Virginia Polytechnic Institute and State University
Year dc:date.issued
1977

Author and committee

dc:creator, dc:contributor.*
Author dc:creator
  • Korcz, Kenneth Walter

Rights

dc:rights
Statement dc:rights
  • In Copyright
Language dc:language.iso
en_US

Identifiers

dc:identifier.*
Handle dc:identifier.uri
http://hdl.handle.net/10919/64632
OAI identifier oai:identifier
oai:vtechworks.lib.vt.edu:10919/64632

Chain of custody

source
Harvested from
Virginia Tech
Base URL
vtechworks.lib.vt.edu/oai/request
Last updated
2026-07-22
Source record
OAI-PMH GetRecord
related terms
citation

Korcz, Kenneth Walter. Determination of economic shelf life of spent nuclear fuel. masters thesis, Virginia Polytechnic Institute and State University, 1977. http://hdl.handle.net/10919/64632