ACTIVATION OF PRIMARY COOLANT IN MOLTEN-SALT REACTOR

Technical Report · Thu Jul 30 04:00:00 EDT 1959

DOI:https://doi.org/10.2172/4227746· OSTI ID:4227746

McGoff, D J; Aronchick, M P; Durrill, P L; Suehrstedt, R A

Estimates were made of the neutron and gamma dose rates at the surface of the secondary heat exchanger of the proposed Molten Salt Reactor due to activation of the primary coolant. Two possible primary coolants were considered: liquid sodium and a molten solution of the fluorides of lithium and beryllium. It was found that no significant neutron currents exist at the heat exchanger surface if either coolant is used. Significant gamma currents exist, however, due to the gamma radiation accompanying the decay of Na/sup 24/ or F/sup 20/. Estimates of the dose rates due to these currents are given. The results showed that if molten salt rather than sodium is used as coolant, lower initial activity will exist at the surface of the secondary heat exchanger and a shorter radioactive decay time will be required for the activity to drop to a safe level. (auth)

• Research Organization: Massachusetts Inst. of Tech., Oak Ridge, Tenn. Engineering Practice School
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-13-018653
• OSTI ID: 4227746
• Report Number(s): MIT-OR-1
• Country of Publication: United States
• Language: English

Related Subjects

ACTIVATION
BERYLLIUM FLUORIDES
CONTAMINATION
COOLANTS
FLUORINE 20
FUSED SALT FUEL
HEAT EXCHANGERS
LIQUID METAL COOLANT
LITHIUM FLUORIDES
RADIATION DOSES
RADIATION PROTECTION
RADIOACTIVITY
REACTORS
SODIUM
SODIUM 24