facility (HFEF) was initiated. As previously reported to the committee, this project was completed on schedule and within the originally authorized funding. A stainless steel reflector was installed to increase the basic test capacity of the EBR-II by approximately 20 percent. In addition, 20 high worth control rods were procured by fixed price contracting from industry to further increase the plant capacity factor by increasing the length of the reactor operating cycle. Neutron flux and temperature variations have been reduced in key experimental assemblies through increased knowledge of core neutronics and core hydraulics characteristics. The ability to detect and locate a test fuel failure has been significantly improved. A second instrumented facility permitting accurate measurement of factors such as coolant flow, fuel temperature and test of in-core instrumentations has been activated. A third instrumented facility is being fabricated and is scheduled for completion in July 1973. There are now 800 fuel pins and over 100 other experiments undergoing fast neutron irradiation in EBR-II. FFTF RESEARCH AND DEVELOPMENT The fiscal year 1974 request for research and development support for the fast flux test facility (FFTF) is $544.2 million—a decrease of $1.4 million from the current fiscal year 1973 estimate. This activity provides funding for the direction of a strong project oriented development effort-which is a vital requirement for the successful design, construction and operation of the FFTF and for FFTF plant-expense-funded components. During fiscal year 1974, within the overall funding request, the research and development activities associated with the project will be diminishing, but there will be offsetting increases because of the delivery of expensed-funded items for which contracts were initiated during fiscal year 1971–73. Other work in fiscal year 1974 will include training for reactor plant operators, systems and component testing, and the preparation of the test program documentation. Engineering efforts associated with the analysis and evaluation of component tests and development and with the preparation of operating procedures for the FFTF and related facilities will also be increased in fiscal year 1974. The overall arrangement of the FFTF is shown below, along with an aerial view of the site as it looked in February of this year. The basic design characteristics of the facility are shown in the accompanying charts. SA-516, GRADE 60 STEEL CYLINDER, ELLIPSOIDAL HEAD 135 FT. DIAMETER x 187 FT. HIGH 12 @ 33 MW 258°F 850°F 12 @ 33 MW 41,000 GPM 42,730 GPM ARGON FFTF BASIC FACILITY DESIGN CHARACTERISTICS (CONT'D) VERTICAL, 91 LATTICE POSITIONS WITH 73 DRIVER 12 FT. OVERALL, 3 FT. FUEL 95 INCHES 20-30 VOLUME % PuO2 70-80 VOLUME % UO2 45,000 MWD/TONNE AVERAGE IN-CORE OPEN TEST POSITIONS 8 INITIAL FLUX 0.7 x 1016 TO ADVANCED CORES OF ≥1016 NV 4 CELLS (WITH CAPABILITY TO ADD 2 MORE) |