b'A P P E N D I X BReactorLast Day of Name Acronym S t a r t u p OperationSpecial Power Excursion Reactor Test No. II (continued)importance in Canada, Europe, and the United States. Also, heavy water tests allowed for the verification of various types of physics calculations on the effects of neutron lifetime on power excursions.41. Special Power Excursion Reactor Test No. III SPERT-III 12-19-58 June 1968SPERT-III was considered the most versatile facility yet developed for studying the inherent safety characteristics of nuclear reactors. This reactor (which was planned as the third in the series of SPERTreactors, but was built second) provided the widest practical range of control over three variables: temperature, pressure, and coolant flow. The reactor sat in a pressurized vessel similar to those used in commercial power production. Water could flow through the vessel at rate up to 20,000 gallons per minute, temperatures up to 650 F, and pressures up to 2,500 pounds per square inch.42. Special Power Excursion Reactor Test No. IV SPERT-IV 7-24-62 August 1970SPERT-IV was an open-tank, twin-pool facility that permitted detailed studies of reactor stability as affected by varying conditions including forced coolant flow, variable height of water above the core, hydrostatic head, and other hydrodynamic effects. The reactor, water-moderated and -reflected, used highly enriched, aluminum alloyed, plate-type fuel elements. The SPERT-IV facility was modified by the installation of a Capsule Driver Core (CDC), which permitted fuel samples to be inserted into a test hole in the center of the reactor core, where it could be subjected to short-period excursions without damaging the driver fuel in the rest of the core. The CDC work on fuel-destructive mechanisms continued until the Power Burst Facility replaced it. 43. Spherical Cavity Reactor Critical Experiment SCRCE November 1973SCRCE was the final experiment in reactor physics work for the NASA-sponsored program to determine1972the feasibility of a reactor going critical with a gaseous core of uranium. Previous work had been done with a cylindrical configuration because of its ease of construction. The spherical configuration was the culmination of the project, allowing for a comparison between theory and experimental results. The spherical shape was considered a more likely geometry for the ultimate application in a rocket to Mars.44. Stationary Low-Power Reactor (Earlier name - A rgonne Low Power Reactor) SL-1, ALPR 8-11-58 1-3-61The SL-1 reactor, originally named Argonne Low Power Reactor (ALPR), was designed for the U.S. Army as a prototype of a low-power, boiling-water reactor plant to be used in geographically remote locations. The SL-1 was accidentally destroyed and three men killed on January 3, 1961.45. Submarine Thermal Reactor S1W, STR 3-30-53 10-17-89With the S1W, also known as the Submarine Thermal Reactor (STR), the United Statesnuclear navy was born.The purpose of a nuclear-powered submarine was to transform submarines into true submersibles, vesselsthat could remain underwater powered by a fuel which did not require oxygen. The S1W (submarine, first prototype, Westinghouse) nuclear power plant was the first prototype built at the Naval Reactors Facility. Cooled and moderated by pressurized water, the reactor and its associated propulsion equipment were installed inside two hull sections duplicating the size and specifications of USS Nautilus, under constructionat the same time in Connecticut. To facilitate shielding research, the hull sections were placed in a tank of water.After startup, the S1Waccomplished a simulated voyage nonstop from Newfoundland to Ireland, submerged and at full power most of the way during the 96 hour test. The simulation proved the principle and the feasibility of atomic ship propulsion long before USS Nautilusset out to sea. Later, the S1W tested advanced design equipment and operated as part of the Navys personnel training program.46. Systems for Nuclear Auxiliary Power (SNAP) 10A Transient No. 1 S N A P TRA N - 1 Early 1960s The SNAPTRAN program extended the SPERT reactor safety testing program to aerospace applications. Three test series, involving three reactors, investigated the behavior of SNAP10A/2 fuel under large-transient,267'