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Design experience: FFTF shielding

Description: The Fast Flux Test Facility is being built to serve as the primary test facility in the United States for the development of liquid-metal-cooled fast breeder reactors. Shield design philosophy for the reactor was to protect permanent structural members with removable or replaceable components. Significant studies were undertaken to establish the shield design in the reactor support area, to protect the core support structure, and to prevent excessive activation of secondary sodium. Equipment associated with each of the three heat transport system loops are contained in separate shielded cells to permit individual shutdown and isolation maintenance. Design-basis source strengths were calculated and dose rate criteria were established based on anticipated access requirements to provide a basis for the design of plant shields. High density concretes were employed in some walls because of physical contraints established by the limited size of the containment building. Extensive shield acceptance tests are planned to establish the radiation environment throughout the reactor and plant to assure satisfactory performance and for subsequent comparison with design values.
Date: November 1, 1978
Creator: Bunch, W.L.; Rathbun, J.L. & Swenson, L.D.
Partner: UNT Libraries Government Documents Department

Initial physics measurements on FFTF

Description: Initial criticality of the Fast Flux Test Facility (FFTF) was achieved on February 9, 1980 at 3:45 p.m. During the period November 27, 1979 to March 8, 1980, fuel was loaded into the FFTF core, initial criticality was achieved, and several subcritical physics measurements were performed. The data obtained from initial FFTF nuclear operation are presented. Specifically, the absolute and relative neutron count rates were predicted for the bulk of the seventy-three fuel loadings of FFTF. Agreement between predicted and observed values is illustrated. Severe variations of fission chamber detection efficiency in the reactor shield is contrasted with that near the core center. Control rod worths, measured by the rod drop inverse kinetics method, are compared with predictions based upon Engineering Mockup Critical (EMC) evaluations. Control rod reactivity worth curves measured by rod run-in inverse kinetics are given.
Date: January 1, 1980
Creator: Bennett, R.A.; Daughtry, J.W.; Harris, R.A.; Jones, D.H.; King, T.L.; Midgett, J.C. et al.
Partner: UNT Libraries Government Documents Department