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Title: Flashing Slurry Releases

Abstract

The Hanford K Basin Closure Project involves the retrieval, transfer and processing of radioactive contaminated slurries containing partially corroded spent nuclear fuel from the K Basin spent fuel pools. The spent fuel is primarily metallic fuel from the operation of the Hanford reactors. The Sludge Treatment Project is being designed to treat and package this material in preparation for ultimate disposal. The processing of the contaminated slurries includes further corrosion of the remaining uncorroded uranium metal in a large heated vessel to form a more stable metal oxide for packaging and storage.

Authors:
;
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
919986
Report Number(s):
PNNL-SA-55037
830403000; TRN: US0806542
DOE Contract Number:
AC05-76RL01830
Resource Type:
Conference
Resource Relation:
Conference: EFCOG 17th Annual Safety Analysis Working Group Workshop, 10 pages
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CLOSURES; CORROSION; FLASHING; NUCLEAR FUELS; OXIDES; PACKAGING; PROCESSING; SLUDGES; SLURRIES; SPENT FUELS; STORAGE; URANIUM

Citation Formats

Schmitt, Bruce E., and Young, Jonathan. Flashing Slurry Releases. United States: N. p., 2007. Web.
Schmitt, Bruce E., & Young, Jonathan. Flashing Slurry Releases. United States.
Schmitt, Bruce E., and Young, Jonathan. Wed . "Flashing Slurry Releases". United States. doi:. https://www.osti.gov/servlets/purl/919986.
@article{osti_919986,
title = {Flashing Slurry Releases},
author = {Schmitt, Bruce E. and Young, Jonathan},
abstractNote = {The Hanford K Basin Closure Project involves the retrieval, transfer and processing of radioactive contaminated slurries containing partially corroded spent nuclear fuel from the K Basin spent fuel pools. The spent fuel is primarily metallic fuel from the operation of the Hanford reactors. The Sludge Treatment Project is being designed to treat and package this material in preparation for ultimate disposal. The processing of the contaminated slurries includes further corrosion of the remaining uncorroded uranium metal in a large heated vessel to form a more stable metal oxide for packaging and storage.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Mar 14 00:00:00 EDT 2007},
month = {Wed Mar 14 00:00:00 EDT 2007}
}

Conference:
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  • This paper provides an overview of the project ``Research on the dispersion of two-phase flashing releases--FLADIS.`` A total of 20 European groups from research institutes and universities have contributed directly or indirectly to the project. During the project considerable progress has been made in the understanding of some special phenomena in dense gas dispersion: effects of two-phase flashing releases, obstacle effects, dense gas dispersion on slopes and concentration variability. Various research tools have been applied apart from theoretical analysis: wind-tunnel experiments, models based on the shallow water equations and 3-dimensional fluid dynamics codes. Parallel to the main FLADIS-project, field experimentsmore » were carried out on flashing releases of pressure-liquefied ammonia.« less
  • To develop design procedures for predictin pressure drops in conduits carrying three-phase flashing flows, a model has been developed at Oak Ridge National Laboratory (ORNL) that is based on the current state of the art. This model has been tailored to consider coal liquids with gases and solids present. The investigation has examimed the fluid dynamics in the let-down valve area of a coal liquefaction plant by assuming a one-dimensional steady-state model. The coal liquids are modeled as a mixture of pseudocomponents in an approach similar to that used by the petroleum industry. Boiling points are chosen to characterize pseudocomponentmore » fractions. Previous studies at ORNL have shown that, for a mixture of hydrogen gas, methane, and a coal-derived liquid, empirical correlations by Wilson and coworkers best predict critical pressures, temperatures, and acentric factors for the pseudocomponents. These properties are needed to perform flash calculations that use the Redlich-Kwong-Soave equation of state and a modified Grayson-Streed method. Reasonable agreement was found between experimental results and the theoretical flash calculations. Energy and mass balances used in the flash calculations interact with a momentum balance to obtain the pressure drop and gas-to-slurry ratio for each interval of length along the flow path. Since there is a possibility of choked flow at each interval of flow length, a calculation of critical flow velocity is also made.« less
  • The results of twelve tests on the vacuum flash system of Process Development Unit P-99 performed during SRC-II processing of an 11% ash Ireland Mine Coal are discussed. The objective of this work was to obtain vacuum flash separation data at well-defined flash zone pressures on slurry produced from Ireland Mine coal in order to supplement 12 earlier experiments on this coal in which problems arose in the measurement of pressures in the vacuum column. The 900/sup 0/F distillate content of the vacuum bottoms and the percent of feed slurry flashed overhead correlated well with flash zone operating conditions. Themore » data for the 11% ash Ireland Mine coal were very similar to those for the Powhatan No. 6 Mine coal. Data for the Powhatan No. 5 Mine (9% ash) and the previous shipment of Ireland Mine (16% ash) coals were quite different compared to results for the other coals due to different levels of ash in these coals and, hence, significantly different vacuum column feed slurry compositions. Polymerization and cracking appeared to be negligible. Specific gravity and melting point of the products correlated well with vacuum column operating conditions. Elemental, distillation, and solvent balances showed the data to be of reasonably good quality.« less