Quarterly Progress Report for the Period April 1, 1958 to June 30, 1958

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The principle progess during the second quarter of 1958 consisted of: accelerating the planning, scheduling, and coordination of the process-water and in-pile test loop irradiation programs; performing two-enrichment non-cycled core studies to determine the improvement in the radial hot channel factor over that which would apply for a uniform core; recalculating the contribution of control to the temperature coefficient using better thermal constant values and an improved method of obtaining control rod worths; performing a burnup analy sis of the reference control rod program to determine the effect of the program on the nuclear hot channel factor; comparing the decontaminating ... continued below

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Pages: 134

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Coen, I. H. & Garbe, R. W. July 30, 1958.

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Description

The principle progess during the second quarter of 1958 consisted of: accelerating the planning, scheduling, and coordination of the process-water and in-pile test loop irradiation programs; performing two-enrichment non-cycled core studies to determine the improvement in the radial hot channel factor over that which would apply for a uniform core; recalculating the contribution of control to the temperature coefficient using better thermal constant values and an improved method of obtaining control rod worths; performing a burnup analy sis of the reference control rod program to determine the effect of the program on the nuclear hot channel factor; comparing the decontaminating abilities of two promising ion-exchange resins using a synthetic corrosion product mixture; establishing a basic permanganate-citrate decontamination procedure which will provide a safe and efffcient method of descaling the stainless steel primary coolant piping; investigating alternate fuel assembly designs to eliminate the possibility of excessive thermal bowing of the assembly which could result in impeding the movement of an adjacent control rod; determining flow and power output at any instant during a two-pump loss-of-coolant-flow accident; calculating the effect of local boiling on pressure drop and coolant flow distribution and the maximum possible volume of local boiling; performing visual flow studies and pressure drop measurements on a onetwelfth scale plastic reactor vessel model; investigating methods of improving the creep strength of silverindium-cadmium control rod alloy by increasing grain size; initiating the preparation of a digital computer code to represent the transient behavior of the steam pressurizer; experimentally determining reactor parameters by measuring the reactor response to a variable by reactor period and control rod position change and by obtaining flux measurements using a variety of foil and wire detectors; modifying the in-pile test loop based on information obtained from visits to the loop fabricator and the Materials Testing Reactor; disassembling, identifying, and examining the second group of process-water specimens removed from the MTR; and performing post-irradiation measurements, collecting fission gases, and metallographically examining the ferrule brazes on two of the four specimens in the second group. Section-A of the Appendix contains the latest revised mechanical, thermal, and nuclear design data for the first core. Section-B, "Information Availability," reviews the accessibility to the Westinghouse Atomic Power Department and the Yankee Atomic Electric Company of documents and reports pertaining to nuclear power reactors. The quantities and types of reports and microfilms received by the Yankee Atomic Electric Company and Westinghouse Atomic Power Department during the second quarter of 1958 are also given in this section. Section-C contains abstracts of trip reports written as a result of visits made by Westinghouse APD and YAEC personnel during the second quarter of 1958 to nuclear testing facilities, vendors locations, and installations of AEC contractors. (For precsding period see YAEC-65.) (auth)

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Pages: 134

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  • Other Information: For Yankee Atomic Electric Co. Orig. Receipt Date: 31-DEC-59

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  • Report No.: YAEC-87
  • Grant Number: AT(30-3)-222, SUBCONTRACT NO. 1
  • DOI: 10.2172/4262223 | External Link
  • Office of Scientific & Technical Information Report Number: 4262223
  • Archival Resource Key: ark:/67531/metadc1020004

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • July 30, 1958

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

Description Last Updated

  • Jan. 17, 2018, 2:57 p.m.

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Coen, I. H. & Garbe, R. W. Quarterly Progress Report for the Period April 1, 1958 to June 30, 1958, report, July 30, 1958; Pittsburgh, Pennsylvania. (digital.library.unt.edu/ark:/67531/metadc1020004/: accessed November 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.