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Title: Dissolution of Material Test Reactor Fuel in an H-Canyon Dissolver

Abstract

In an amended record of decision for the management of spent nu clear fuel (SNF) at the Savannah River Site, the US Department of Energy has authorized the dissolution and recovery of U from1000 bundles of Al-clad SNF. The SNF is fuel from domestic and foreign research reactors and is typically referred to as Material Test Reactor (MTR) fuel. Bundles of MTR fuel containing assemblies fabricated from U-Al alloys (or other U compounds) are currently dissolved using a Hg-catalyzed HNO 3 flowsheet. Since the development of the existing flow sheet, improved experimental methods have been developed to more accurately characterize the offgas composition and generation r ate during laboratory dissolutions. Recently, these new techniques were successfully used to develop a flowsheet for the dissolution of High Flux Isotope Reactor (HFIR) fuel. Using the data from the HFIR dissolution flowsheet development and necessary laboratory experiments, the Savannah River National Laboratory (SRNL) was requested to define flowsheet conditions for the dissolution of MTR fuels. With improved offgas characterization techniques, SRNL will be able define the number of bundles of fuel which can be charged to an H-Canyon dissolver with much less conservatism.

Authors:
 [1];  [1];  [1]
  1. Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
Publication Date:
Research Org.:
Savannah River Site (SRS), Aiken, SC (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1457681
Report Number(s):
SRNL-STI-2016-00725
DOE Contract Number:  
AC09-08SR22470
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English

Citation Formats

Rudisill, T. S., Daniel, W. E., and O'Rourke, P. E. Dissolution of Material Test Reactor Fuel in an H-Canyon Dissolver. United States: N. p., 2018. Web. doi:10.2172/1457681.
Rudisill, T. S., Daniel, W. E., & O'Rourke, P. E. Dissolution of Material Test Reactor Fuel in an H-Canyon Dissolver. United States. doi:10.2172/1457681.
Rudisill, T. S., Daniel, W. E., and O'Rourke, P. E. Wed . "Dissolution of Material Test Reactor Fuel in an H-Canyon Dissolver". United States. doi:10.2172/1457681. https://www.osti.gov/servlets/purl/1457681.
@article{osti_1457681,
title = {Dissolution of Material Test Reactor Fuel in an H-Canyon Dissolver},
author = {Rudisill, T. S. and Daniel, W. E. and O'Rourke, P. E.},
abstractNote = {In an amended record of decision for the management of spent nu clear fuel (SNF) at the Savannah River Site, the US Department of Energy has authorized the dissolution and recovery of U from1000 bundles of Al-clad SNF. The SNF is fuel from domestic and foreign research reactors and is typically referred to as Material Test Reactor (MTR) fuel. Bundles of MTR fuel containing assemblies fabricated from U-Al alloys (or other U compounds) are currently dissolved using a Hg-catalyzed HNO3 flowsheet. Since the development of the existing flow sheet, improved experimental methods have been developed to more accurately characterize the offgas composition and generation r ate during laboratory dissolutions. Recently, these new techniques were successfully used to develop a flowsheet for the dissolution of High Flux Isotope Reactor (HFIR) fuel. Using the data from the HFIR dissolution flowsheet development and necessary laboratory experiments, the Savannah River National Laboratory (SRNL) was requested to define flowsheet conditions for the dissolution of MTR fuels. With improved offgas characterization techniques, SRNL will be able define the number of bundles of fuel which can be charged to an H-Canyon dissolver with much less conservatism.},
doi = {10.2172/1457681},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed May 16 00:00:00 EDT 2018},
month = {Wed May 16 00:00:00 EDT 2018}
}

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