Tests were performed to obtain station performance data at various steady-state generator loads. The station 0 was operated for four-hour periods at steady state conditions and levels of 5, 21, 42, and 61 Mw gross generator output. The various readings are presented in tabular form. A list is given of equipment in service during the test. All plant components operated satisfactorily during the test. (M.C.G.)

The power of high flux fuel assemblies and three-tube drivers planned for future operations is limited by the burnout safety factor (BOSF). In the past, the power of standard production fuel assemblies was limited almost always by one of the hydraulic limits, and in most cases the assemblies operated at powers significantly below that permitted by the BOSF limit. The burnout conditions for an ``ideal`` fuel surface have been well established in mockups at SRL and Columbia University. Little experimental data are available on nonidealities (such as local hot spots), although calculated factors are applied to the BOSF to account for certain nonidealities. Because of operation at the BOSF limit, better knowledge is needed of the effects of nonidealities and other factors on heat transfer burnout of fuel surfaces. This memorandum presents a program designed to give a better understanding of BOSF.

The objective of this test authorization is to increase reactivity and thus reduce short term enrichment requirements by increasing graphite temperature limits during low exposure operation following full central zone discharge.

This report discusses the delayed neutron characteristics of a reactor which are a function of the distribution of fissions in the various fissionable isotopes. The delayed neutron characteristics of the NPRL delayed fraction and decay constants, are presented as functions of exposure to 2000 MWD/T for both room temperature and operating temperature. It is of importance to note that the delayed neutron fraction decreases from 0.693% to 0.539% with increased exposure. Thus 22% less reactivity change represents a prompt critical condition at 2000 MWD/T, compared to the zero exposure condition.

This document presents experimental data obtained during a series of tests which were completed at 105-D and DR Reactors in February and March, 1960. No analysis of the data is included in this document. The tests were: PT-301-I, II -- Reactor cold, full flow, BPA power failure; PT-278-A, III B -- 1170 MW, full flow, BPA power failure; and PT-278-A, II -- 1190 MW, full flow, poison push causing bulk surge and scram.

The voltage and frequency response of selected SM-1 plant system parameters to step load changes was analyzed using analog computer measurements. The analog model was that developed for analysis of the SM-2 design. The approach to the analysis, formulation of the model, and analog recordings are presented. The data will be used to prove reliability of the analog model by comparing analog data with test data to be taken at SM-1. (auth)

None

Low attack rates (0.1 to 0.5 mpy) were displayed by coupon specimens of type 347 stainless steel, titanium RC-55, and Zircaloy-2 which were exposed for 2877.5 hr in an oxygenated slurry of Th--8% U oxide, 116.5 hr in water, 6.9 hr in 5% HNO/sub 3/, and 4.3 hr in 3% triscdium phosphate during mns SM-6 through SM-9 in the slurry blanket mockup. The leading coupon of type 347 stainless steel showed a slightly higher rate than the other stainless steel ccupons due to entrance effects. Specimens of SA-212-B carbon steel displayed average attack rates of 2.9 mpy. (auth)

This memorandum provides the minutes of the 7th meeting of the Livermore Vulnerability Committee. The Laboratory commitments in the Tapestry experiment, with particular reference to those experiments proposed in the Polaris MK 2 and the Minuteman MK 2 programs.