Open AccessThermal analysis to support decommissioning of the molten salt reactor experiment
Author(s) -
C. D. Sulfredge,
David G. Morris,
J. E. Park,
Paul T. Williams
Publication year - 1996
Language(s) - English
Resource type - Reports
DOI - 10.2172/245567
Subject(s) - nuclear engineering , nuclear decommissioning , charcoal , waste management , environmental science , heat transfer , work (physics) , chemistry , mechanics , engineering , mechanical engineering , physics , organic chemistry
As part of the decommissioning process for the Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory, several thermal-sciences issues were addressed. Apparently a mixture of UF{sub 6} and F{sub 2} had diffused into the upper portion of one charcoal column in the MSRE auxiliary charcoal bed (ACB), leading to radiative decay heating and possible chemical reaction sources. A proposed interim corrective action was planned to remove the water from the ACB cell to reduce criticality and reactivity concerns and then fill the ACB cell with an inert material. This report describes design of a thermocouple probe to obtain temperature measurements for mapping the uranium deposit, as well as development of steady-state and transient numerical models for the heat transfer inside the charcoal column. Additional numerical modeling was done to support filling of the ACB cell. Results from this work were used to develop procedures for meeting the goals of the MSRE Remediation Project without exceeding appropriate thermal limits