Liquid Metal Operations

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Throughout its existence, Area IV supported non-nuclear research and development programs. Primarily, these programs focused on testing liquid metal processes and developing liquid metal components (e.g., pumps, sodium water heat exchangers) and weld testing. This research supported the design of the Hallam Nuclear Power Facility, the Piqua Nuclear Power Facility, the Fast Flux

Sodium at room temperature

Test Facility (FFTF) and the Clinch River Breeder Reactor. Liquid metal components were tested in a non-nuclear environment.

The research primarily involved metallic sodium. Sodium is a metal with a light gray appearance and, at room temperature, is as hard as cold butter. It is found in compound form in table salt; however, elemental sodium is not found in nature. Metallic sodium reacts with water, melts at 208°F and boils at 1618°F.
Sodium was chosen because:

It has excellent heat transfer properties
Has a low operating pressure when compared to water
Has a low melting point
It can be pumped using electromagnetic energy

In some nuclear reactors, the sodium is a cooling agent for the reactor's core. During the 1960's and the 1970's, experiments involving sodium included testing to support national efforts to develop nuclear power and liquid metal related technologies.

Steam Generator Development - Steam Generators transfer heat from a sodium system to a water system to produce steam. This steam generator was designed by Atomics International.	Mechanical Sodium Pumps - research into designing efficient high flow mechanical pumps was performed. Several pumps were developed	Sodium Cold Traps - high sodium purity was maintained by using this device to cool and isolate impurities. This cold trap has been cut open and solid sodium is seen within.
Evaluation a competing steam generator designs – The SCTI was used to test and compare competing engineering designs. The 75 megawatt stream generator on the left was designed by Atomics International while the similar sized unit on the right was designed by Babcox and Wilcox.		Electromagnetic Sodium Pumps - This pump causes sodium to flow using electromagnetic energy without moving parts.
Flow meters - this flow meter measured high flow rates of liquid sodium from the outside of the pipe and had no moving parts.	Few-tube Test Model - tested the concept of incorporating steam leak detection into the tube design of a sodium steam heat exchanger.	Natural Draft heat Exchanger - this heat exchanger tested and engineering design intended to remove residual heat from a sodium system in the event of a sudden shutdown without using electricity.
Japanese sodium pump testing - the sodium pump test facility was used to test two different electro-magnetic sodium pumps for the Japanese.	Sodium Valves - Valves to control high temperature sodium were tested with the results used to evaluate and verify a variety of designs.	Experienced Staff - in 1974, approximately 1,800 people were involved with the engineering, development and testing of sodium components at SSFL. This photograph of ETEC staff was taken in 1986.

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