Molten Salt Reactor Safety Analysis

Molten Salt Reactor Safety Analysis

Presenter

  • George Flanagan, Advanced Reactor Systems and Safety Group
August 15, 2017 - 1:00pm to 2:00pm

Abstract 

The presentation will discuss the approach taken for the safety analysis of the Molten Salt Reactor Experiment (MSRE), which operated at ORNL from 1965 to 1969. Issues associated with the prediction and analysis of the MSRE plant response, particularly with respect to the release of fission products that could pose a hazard to the surrounding population and/or environment, will be discussed. Events and accident sequences specific to molten salt reactors (MSRs) will be discussed, and the differences between MSR accidents and those in light water reactors will be pointed out. Phenomena unique to MSRs that affect the behavior of the plant under accident conditions will be emphasized.

Additional Information 

Refreshments will be served.

Sponsoring Organization 

Reactor and Nuclear Systems Division Seminar

Location

  • Weinberg Auditorium
  • Building: 4500-N
  • Room: I-126

Contact Information

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