skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

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

Abstract

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 detailedmore » 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.« less

Authors:
; ;
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
230260
Report Number(s):
ORNL/TM-13142
ON: DE96008017
DOE Contract Number:  
AC05-96OR22464
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Jan 1996
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; MSRE REACTOR; REACTOR SHUTDOWN; REACTOR COMPONENTS; MOLTEN SALTS; CHEMICAL REACTIONS; RADIATIONS; RADIATION MONITORING; EVALUATION

Citation Formats

Williams, D F, Del Cul, G D, and Toth, L M. A descriptive model of the molten salt reactor experiment after shutdown: Review of FY 1995 progress. United States: N. p., 1996. Web. doi:10.2172/230260.
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. United States. https://doi.org/10.2172/230260
Williams, D F, Del Cul, G D, and Toth, L M. 1996. "A descriptive model of the molten salt reactor experiment after shutdown: Review of FY 1995 progress". United States. https://doi.org/10.2172/230260. https://www.osti.gov/servlets/purl/230260.
@article{osti_230260,
title = {A descriptive model of the molten salt reactor experiment after shutdown: Review of FY 1995 progress},
author = {Williams, D F and Del Cul, G D and Toth, L M},
abstractNote = {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.},
doi = {10.2172/230260},
url = {https://www.osti.gov/biblio/230260}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 1996},
month = {Mon Jan 01 00:00:00 EST 1996}
}