A descriptive model of the molten salt reactor experiment after shutdown: Review of FY 1995 progress

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During FY 1995 considerable progress was made toward gaining a better understanding of the chemistry and transport processes that continue to govern the behavior of the Molten Salt Reactor Experiment (MSRE). As measurements in the MSRE proceed, laboratory studies continue, and better analyses are available, our understanding of the state of the MSRE and the best path toward remediation improves. Because of the immediate concern about the deposit in the auxiliary charcoal bed (ACB), laboratory studies in the past year focused on carbon-fluorine chemistry. Secondary efforts were directed toward investigation of gas generation from MSRE salts by both radiolytic and ... continued below

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66 p.

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Williams, D.F.; Del Cul, G.D. & Toth, L.M. January 1, 1996.

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Description

During FY 1995 considerable progress was made toward gaining a better understanding of the chemistry and transport processes that continue to govern the behavior of the Molten Salt Reactor Experiment (MSRE). As measurements in the MSRE proceed, laboratory studies continue, and better analyses are available, our understanding of the state of the MSRE and the best path toward remediation improves. Because of the immediate concern about the deposit in the auxiliary charcoal bed (ACB), laboratory studies in the past year focused on carbon-fluorine chemistry. Secondary efforts were directed toward investigation of gas generation from MSRE salts by both radiolytic and nonradiolytic pathways. In addition to the laboratory studies, field measurements at the MSRE provided the basis for estimating the inventory of uranium and fluorine in the ACB. Analysis of both temperature and radiation measurements provided independent and consistent estimates of about 2.6 kg of uranium deposited in the top of the ACB. Further analysis efforts included a refinement in the estimates of the fuel- salt source term, the deposited decay energy, and the projected rate of radiolytic gas generation. This report also provides the background material necessary to explain new developments and to review areas of particular interest. The detailed history of the MSRE is extensively documented and is cited where appropriate. This work is also intended to update and complement the more recent MSRE assessment reports.

Physical Description

66 p.

Notes

INIS; OSTI as DE96008017

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  • Other Information: PBD: Jan 1996

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  • Other: DE96008017
  • Report No.: ORNL/TM--13142
  • Grant Number: AC05-96OR22464
  • DOI: 10.2172/230260 | External Link
  • Office of Scientific & Technical Information Report Number: 230260
  • Archival Resource Key: ark:/67531/metadc664872

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • January 1, 1996

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • Jan. 21, 2016, 7:44 p.m.

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Williams, D.F.; Del Cul, G.D. & Toth, L.M. A descriptive model of the molten salt reactor experiment after shutdown: Review of FY 1995 progress, report, January 1, 1996; Tennessee. (digital.library.unt.edu/ark:/67531/metadc664872/: accessed November 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.