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Description: This report describes progress in the USAEC-sponsored Interlaboratory LMFBR Reaction Rate (ILRR) program. This program has been established by RDT to develop a capability to accurately measure neutron-induced reaction rates for LMFBR fuels and materials development programs. The initial goal for the principal fission reactions, {sup 235}U, {sup 238}U, and {sup 239}Pu, is an accuracy to within {+-} 5 at the 95% confidence level. Accurate measurement of other fission and non-fission reactions will be required, but to a lesser accuracy, between {+-} 5 to 10% at the 95% confidence level. A secondary program objective is improvement in knowledge of the nuclear parameters involved in fuels and materials dosimetry measurements of neutron flux, spectra, fluence, and burnup. The accuracy goals of the ILRR program are severe; measurements of fast-neutron-induced reaction rates have not been rapidly moving toward this level of precision. Using a number of techniques in well established neutron environments of current interest for fast reactor development and critically evaluating the results will help establish existing levels of accuracy and indicate the scale of effort required for improvement. To accomplish the objectives of this program, reliable and accepted experimental values of reaction rates and ratios will be determined for various well established and permanent neutron fields. The Coupled Fast Reactivity Measurement Facility (CFRMF) at Aerojet Nuclear Company (ANC) is the first neutron field being studied because of the similarity of its spectrum to that of a fast reactor and the range and reproducibility of flux levels available for track etch, fission chamber, radiochemistry, and helium mass spectrometric measurements. Results of the CFRMF and other ILRR tests coupled with those of past and present EBR-II dosimetry tests will provide the improved and more precise values of nuclear parameters urgently needed for LMFBR fuels and materials development programs.
Date: September 1, 1971
Creator: WN, MCELROY
Partner: UNT Libraries Government Documents Department

Liquid metal bearings technology for large, high-temperature, sodium rotating machinery. Development and test of high-temperature proximity probe for use in liquid sodium. Fourth topical report

Description: An inductance-type, proximity-probe system for measurement of bearing film thicknesses and shaft orbits in high-temperature, liquid-sodium environment has been developed, built and tested. The probe system is designed to operate at temperatures up to 1200/sup 0/F and gap range of 0.004'' to 0.080'', with good linearity over about three-quarters of the range, when using probe pairs connected in push-pull. The probes were tested extensively in both gas and sodium environments, culminating in a 684 hours continuous test in a temperature range of 1050/sup 0/F to 1170/sup 0/F. The probes operated stably, repeatably and without undergoing performance changes.
Date: June 1, 1971
Creator: Hoogenboom, I. & Kissinger, C.
Partner: UNT Libraries Government Documents Department

LMFBR Nuclear Safety Program Annual Report: July 1, 1969, to June 30, 1970

Description: Report issued by the Argonne National Laboratory discussing the Liquid Metal Fast Breeder Reactor Nuclear Safety Program. The work completed by the program between 1969 and 1970 is presented. This report includes tables, illustrations, and photographs.
Date: July 1971
Creator: Simmons, W. R. & Marchaterre, J. F.
Partner: UNT Libraries Government Documents Department

Test and evaluation of Alco/BLH prototype sodium-heated steam generator. Final report

Description: A 30-Mwt prototype sodium-to-sodium intermediate heat exchanger and a 30-Mwt prototype sodium-heated steam generator were tested in combined operation in its Sodium Components Test Installation. This report contains the results of test and evaluation of the steam generator. During plant performance tests, performance degradation was observed, which resulted in the initiation of a diagnostic test series. This test series revealed that under certain operating conditions, the thermohydraulic characteristic of the steam generator changed either suddenly or gradually, resulting in overall performance degradation. A structural failure, requiring retirement of the unit, occurred before the diagnostic test series and analytical support effort were completed. This report describes the thermohydraulic and structural performance, including the structural failures, and related evaluation analyses of the Alco/BLH prototype steam generator performed prior to termination of the test and evaluation program. In addition, the report presents a post-test examination plan to obtain data that could possibly explain the cause of performance anomalies and structural failures experienced during testing.
Date: January 31, 1971
Creator: Kaplan, C.J.; Auge, L.J.; Cho, S.M.; Hanna, R.W.; Prevost, J.R.; Steger, N.A. et al.
Partner: UNT Libraries Government Documents Department