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Title: Advanced dry head-end reprocessing of light water reactor spent nuclear fuel

Abstract

A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80.degree. C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.

Inventors:
; ; ; ;
Publication Date:
Research Org.:
ORNL (Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States))
Sponsoring Org.:
USDOE
OSTI Identifier:
1107878
Patent Number(s):
8,574,523
Application Number:
13/079,897
Assignee:
UT-Battelle, LLC (Oak Ridge, TN) ORNL
DOE Contract Number:
AC05-000R22725
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS

Citation Formats

Collins, Emory D, Delcul, Guillermo D, Hunt, Rodney D, Johnson, Jared A, and Spencer, Barry B. Advanced dry head-end reprocessing of light water reactor spent nuclear fuel. United States: N. p., 2013. Web.
Collins, Emory D, Delcul, Guillermo D, Hunt, Rodney D, Johnson, Jared A, & Spencer, Barry B. Advanced dry head-end reprocessing of light water reactor spent nuclear fuel. United States.
Collins, Emory D, Delcul, Guillermo D, Hunt, Rodney D, Johnson, Jared A, and Spencer, Barry B. 2013. "Advanced dry head-end reprocessing of light water reactor spent nuclear fuel". United States. doi:. https://www.osti.gov/servlets/purl/1107878.
@article{osti_1107878,
title = {Advanced dry head-end reprocessing of light water reactor spent nuclear fuel},
author = {Collins, Emory D and Delcul, Guillermo D and Hunt, Rodney D and Johnson, Jared A and Spencer, Barry B},
abstractNote = {A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gas comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80.degree. C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2013,
month =
}

Patent:

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  • A method for reprocessing spent nuclear fuel from a light water reactor includes the step of reacting spent nuclear fuel in a voloxidation vessel with an oxidizing gas having nitrogen dioxide and oxygen for a period sufficient to generate a solid oxidation product of the spent nuclear fuel. The reacting step includes the step of reacting, in a first zone of the voloxidation vessel, spent nuclear fuel with the oxidizing gas at a temperature ranging from 200-450.degree. C. to form an oxidized reaction product, and regenerating nitrogen dioxide, in a second zone of the voloxidation vessel, by reacting oxidizing gasmore » comprising nitrogen monoxide and oxygen at a temperature ranging from 0-80.degree. C. The first zone and the second zone can be separate. A voloxidation system is also disclosed.« less
  • One alternative for closing the nuclear fuel cycle is efficient, high decontamination separation of uranium and plutonium and fabrication of a Pu-U mixed-oxide fuel. Detailed flowsheets were prepared by Savannah River Laboratory for a conceptual 10 MT/day reprocessing facility. The generation of liquid waste and the associated liquid waste handling facilities for the reprocessing plant were defined. Over 40 individual waste streams were identified. The reference facility generates 6.4 m/sup 3/ (1700 gal) of high-level liquid waste (HLLW) per day, which is converted to 0.5 m/sup 3/ (130 gal) of glass contained in three packages, each 0.3 m (12 in.)more » in diameter x 3 m (10 ft) high. Each operating day, the process converts 2.9 m/sup 3/ (775 gal) of concentrated intermediate-level liquid waste (ILLW) to 4 m/sup 3/ (1050 gal) of cemented solid in 21 carbon steel drums. Large-scale underground tank storage of liquid waste is eliminated by prompt solidification of the HLLW and ILLW. Each container of glass contains 30 kW nuclear decay heat and must be stored in water for an interim period prior to shipment to a federal repository. 10 figures, 1 table.« less
  • The spent fuel pit of a pressured water reactor (PWR) nuclear power plant has sufficient coolant capacity that a safety rated cooling system is not required. A non-safety rated combined cooling and purification system with redundant branches selectively provides simultaneously cooling and purification for the spent fuel pit, the refueling cavity, and the refueling water storage tank, and transfers coolant from the refueling water storage tank to the refueling cavity without it passing through the reactor core. Skimmers on the suction piping of the combined cooling and purification system eliminate the need for separate skimmer circuits with dedicated pumps.
  • The spent fuel pit of a pressured water reactor (PWR) nuclear power plant has sufficient coolant capacity that a safety rated cooling system is not required. A non-safety rated combined cooling and purification system with redundant branches selectively provides simultaneously cooling and purification for the spent fuel pit, the refueling cavity, and the refueling water storage tank, and transfers coolant from the refueling water storage tank to the refueling cavity without it passing through the reactor core. Skimmers on the suction piping of the combined cooling and purification system eliminate the need for separate skimmer circuits with dedicated pumps. 1more » figures.« less
  • As part of the decommissioning of the 324 Building Radiochemical Engineering Cells there is a need to remove commercial Light Water Reactor (LWR) spent nuclear fuel (SNF) presently stored in these hot cells. To enable fuel removal from the hot cells, the commercial LWR SNF will be packaged and shipped to the 200 Area Interim Storage Area (ISA) in a manner that satisfies site requirements for SNF interim storage. This document identifies the criteria that the 324 Building Radiochemical Engineering Cell Clean-out Project must satisfy for acceptance of the LWR SNF by the SNF Project at the 200 Area ISA.more » In addition to the acceptance criteria identified herein, acceptance is contingent on adherence to applicable Project Hanford Management Contract requirements and procedures in place at the time of work execution.« less