PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JUNE 1960

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Solid solutions of uranium oxide containing massive additions of La/sub 2/O/sub 3/ or Y/sub 2/O/sub 3/ are being investigated with respect to their stability in an oxidizing environment at higher temperatures. An investigation is being conducted on the effects of ultrahigh pressure and high temperature on the U-O system and on reactions of uranium oxides with various mixed oxides. Work was continued on the investigation of the effects of fast-neutron irradiation upon the mechanical properties of Type 347 stainless steel. Experimental work was completed in the program to develop a corrosion resistant, high-strength, lowcross-section Nb alloy for pressurized water-reactor applications. ... continued below

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Medium: P; Size: Pages: 104

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Dayton, R.W. & Tipton, C.R. Jr. July 1, 1960.

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Solid solutions of uranium oxide containing massive additions of La/sub 2/O/sub 3/ or Y/sub 2/O/sub 3/ are being investigated with respect to their stability in an oxidizing environment at higher temperatures. An investigation is being conducted on the effects of ultrahigh pressure and high temperature on the U-O system and on reactions of uranium oxides with various mixed oxides. Work was continued on the investigation of the effects of fast-neutron irradiation upon the mechanical properties of Type 347 stainless steel. Experimental work was completed in the program to develop a corrosion resistant, high-strength, lowcross-section Nb alloy for pressurized water-reactor applications. The creep behavior or Zircaloy-2 during irradiation is to be studied by comparing the total creep deformation obtained under reactor conditions and that obtained out of reactor. Friction and wear studies in vacuum, in argon, and in sodium environments were continued for W on W specimens and for Mo on stainless steel coated Na/sub 2/MoO/sub 4/. Corrosion tests of the Nb-U alloys were continued in 600 deg F water with an accumulation of 336 days of exposure. Thorium-uranium and Th-U-base alloys are being investigated with the aim of improving their irradiation stability. Studies of diffusion of fission gases and of iodine in single crystals or fused UO/sub 2/ plates have continued. Methods of fabricating 60 to 90 vol.% UO/sub 2/ cermets to 90% of theoretical density or greater were investigated. Economical methods for producing useful UC components from powders are being studied. Rarther progress in research directed toward preparation of high-purity and high-quality single crystals of UO/sub 2/ was made. The program concerned with obtaining electrical- and thermalconductivity measurements for UO/sub 2/ before and after irradiation was resumed. A study of the corrosion properties of welding alloys for use with Hastelloy F was completed. Data are reported on the stress-rupture strength of Al35 wt.% U alloys. The corrosion of Ta and Ta alloys by liquid Pu alloys is being studied. Research on core materials for both the MGCR and HTGR is in progress. For the MGCR, the major effort is on development and evaluation of UO/ sub 2/ dispersions in BeO and Al/sub 2/O/sub 3/ and dispersions of UC or UC/sub 2/ in graphite. For the HTGR vapor deposition is being investigated as a method of preparing and coating UC and ThC powder. Techniques are being developed for the preparation of instrumented SM-1. Type fuel plates for in-pile test evaluation. Materials were selected, fabrication techniques developed, and specifications written for the production of SM-2 fuel plates. A study is being made of the processing variables in the fabrication of BeOUO/sub 2/ ceramics. The study of the radiation stability of various potential ML-1 fuel material is progressing. The corrosion of Th and U under storage conditions is being investigated. An investigation of the behavior of Pu in a pyrometallurgical process developed for the recovery of U from spent fuel elements was completed. (For preceding period see BMI-1442.) (W.L.H.)

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Medium: P; Size: Pages: 104

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  • Other Information: Orig. Receipt Date: 31-DEC-60

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  • Report No.: BMI-1448(Rev.)
  • Grant Number: None
  • DOI: 10.2172/4161788 | External Link
  • Office of Scientific & Technical Information Report Number: 4161788
  • Archival Resource Key: ark:/67531/metadc872497

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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.

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Creation Date

  • July 1, 1960

Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

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  • Nov. 18, 2016, 7:23 p.m.

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Dayton, R.W. & Tipton, C.R. Jr. PROGRESS RELATING TO CIVILIAN APPLICATIONS DURING JUNE 1960, report, July 1, 1960; Columbus, Ohio. (digital.library.unt.edu/ark:/67531/metadc872497/: accessed June 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.