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Title: 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:
 [1]
  1. 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}
}

Works referenced in this record:

Immobilisation of high level nuclear reactor wastes in SYNROC
journal, March 1979


Immobilization of high-level waste in ceramic waste forms
journal, July 1986

  • Ringwood, Alfred Edward; Kelly, P. M.
  • Philosophical Transactions of the Royal Society of London. Series A, Mathematical and Physical Sciences, Vol. 319, Issue 1545, p. 63-82
  • https://doi.org/10.1098/rsta.1986.0086

Uniaxial hot-pressing in bellows containers
journal, January 1983