Container for reprocessing and permanent storage of spent nuclear fuel assemblies
Abstract
A single canister process container for reprocessing and permanent storage of spent nuclear fuel assemblies comprising zirconium-based cladding and fuel, which process container comprises a collapsible container, having side walls that are made of a high temperature alloy and an array of collapsible support means wherein the container is capable of withstanding temperature necessary to oxidize the zirconium-based cladding and having sufficient ductility to maintain integrity when collapsed under pressure. The support means is also capable of maintaining their integrity at temperature necessary to oxide the zirconium-based cladding. The process container also has means to introduce and remove fluids to and from the container.
- Inventors:
-
- Oak Ridge, TN
- Issue Date:
- Research Org.:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 868203
- Patent Number(s):
- 5098645
- Assignee:
- United States of America as represented by United States (Washington, DC)
- Patent Classifications (CPCs):
-
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- DOE Contract Number:
- AC05-84OR21400
- Resource Type:
- Patent
- Country of Publication:
- United States
- Language:
- English
- Subject:
- container; reprocessing; permanent; storage; spent; nuclear; fuel; assemblies; single; canister; process; comprising; zirconium-based; cladding; comprises; collapsible; walls; temperature; alloy; array; support; means; capable; withstanding; oxidize; sufficient; ductility; maintain; integrity; collapsed; pressure; maintaining; oxide; introduce; remove; fluids; fuel assemblies; nuclear fuel; spent nuclear; support means; permanent storage; remove fluids; temperature alloy; assemblies comprising; container comprises; /376/250/
Citation Formats
Forsberg, Charles W. Container for reprocessing and permanent storage of spent nuclear fuel assemblies. United States: N. p., 1992.
Web.
Forsberg, Charles W. Container for reprocessing and permanent storage of spent nuclear fuel assemblies. United States.
Forsberg, Charles W. Wed .
"Container for reprocessing and permanent storage of spent nuclear fuel assemblies". United States. https://www.osti.gov/servlets/purl/868203.
@article{osti_868203,
title = {Container for reprocessing and permanent storage of spent nuclear fuel assemblies},
author = {Forsberg, Charles W},
abstractNote = {A single canister process container for reprocessing and permanent storage of spent nuclear fuel assemblies comprising zirconium-based cladding and fuel, which process container comprises a collapsible container, having side walls that are made of a high temperature alloy and an array of collapsible support means wherein the container is capable of withstanding temperature necessary to oxidize the zirconium-based cladding and having sufficient ductility to maintain integrity when collapsed under pressure. The support means is also capable of maintaining their integrity at temperature necessary to oxide the zirconium-based cladding. The process container also has means to introduce and remove fluids to and from the container.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1992},
month = {1}
}
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Immobilization of high-level waste in ceramic waste forms
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Uniaxial hot-pressing in bellows containers
journal, January 1983
- Ringwood, A. E.; Major, A.; Ramm, E. J.
- Nuclear and Chemical Waste Management, Vol. 4, Issue 2