Quarterly Progress Report for the Period July 1 to September 30, 1958 Page: 9 of 113
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This report contains a technical description of the research and development
work accomplished and the progress made during the period from July 1 to
September.30, 1958 under the Research and Development Program as presented in
YAEC Development Program:Report YAEC-61 Revision-l for the.second half of 1958.
An evaluation and the resulting conclusions of work performed are given for
each project in which definitive progress has been made.
The principle progress during the third quarter of 1958 consisted of:
1. Obtaining promising fuel fabrication results from production scale
investigations of simplified UO preparations.methods, presintering operation
elimination, increasing pellet. ensities and reductions of UO2 losses.
2. Successfully brazing a ninety-five inch long experimental fuel subassembly
in which all joints, including outside ferrules and control rod rubbing
strips, had brazed fillets.
3. Completing the fabrication of the last group of MTR process water irradiation
samples and.all of the in-pile test loop samples except for the specimens
containing 27% enriched pellets.
4. Performing a nuclear analysis of various fuel assembly designs as part of
an overall evaluation of fuel assembly bowing in the Yankee reactor.
5. Completing corrosion studies of primary plant materials in static autoclaves
to aid in the selection of a pH control agent.
6. Developing a "Compromise Design" for the fuel assembly which incorporates
a series of small design changes to eliminate the possibility of restricting
control rod motion by interference due to a superposition of bowing of the
fuel assembly and an adverse accumulation of mechanical tolerances.
7. Completing the calculation of the following first core kinetic parameters:
moderator temperature coefficient, the Doppler temperature coefficient,
the void coefficient, neutron lifetime and delayed neutron fraction.
8. Obtaining flux profiles, flux peaking, flux spectrum, peripheral fuel rod
worth, void coefficient, temperature.coefficient and control rod worth data
from the Critical Reactor Experiments with a 3:1-water-to-uranium metal
ratio core at the Westinghouse Reactor Evaluation Center.
9. Continuing instrumentation and individual component operational testing
of the in-pile test loop.
10. Analyzing the results of the post-irradiation examination of the second
group ,Of process water samples and delivery of the last group of samples
to the MTR.
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Garbe, R. W. & Walchli, H. E. Quarterly Progress Report for the Period July 1 to September 30, 1958, report, October 31, 1959; Pittsburgh, Pennsylvania. (https://digital.library.unt.edu/ark:/67531/metadc1017843/m1/9/: accessed May 19, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.