Research and development activities, waste fixation program. Quarterly progress report, July--September 1973

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The aim of the melt development program is to produce meltformed ceramic products that have the optimum combination of physical properties for the fixation of radioactive wastes. Depending on thermal treatment many of the ceramics can be in either a glassy or a microcrystalline form. Laboratory and nonradioactive pilot plant tests are being conducted to evaluate both forms. Both PW-4b and PW-6 waste compositions were successfully solidified into borosilicate glass in the development spray solidifier. Calciner wall scaling was minimal and off-gas filter differential pressure remained low during over 26 hours operation in five runs. Glass formation and discharge from ... continued below

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Pages: 53

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Platt, A. M. October 1, 1973.

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  • Pacific Northwest Laboratory
    Publisher Info: Battelle Pacific Northwest Labs., Richland, Wash. (USA)
    Place of Publication: Richland, Washington

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The aim of the melt development program is to produce meltformed ceramic products that have the optimum combination of physical properties for the fixation of radioactive wastes. Depending on thermal treatment many of the ceramics can be in either a glassy or a microcrystalline form. Laboratory and nonradioactive pilot plant tests are being conducted to evaluate both forms. Both PW-4b and PW-6 waste compositions were successfully solidified into borosilicate glass in the development spray solidifier. Calciner wall scaling was minimal and off-gas filter differential pressure remained low during over 26 hours operation in five runs. Glass formation and discharge from the melter proceeded smoothly at melt temperatures ranging from 1050 to 1175 deg C. Discussions were held with glass industry representatives concerning the design and fabrication of electric glass tanks for the vitrification of high-level wastes. Melting tests in an industrial electric glass tank are planned to check the feasibility of this approach and to obtain design data; a laboratory-scale unit has also been constructed to gain firsthand experience. A series of tests and a stress analysis have shown with good assurance that the leaks which have appeared in the thermowells of several of the WSEP canisters are located at the weld where the thermowells enter the canisters. The welds are located well above the product level in the canisters and the failures are due to stress rather than corrosion. Calculations of helium buildup in waste glass canisters indicate that internal stresses due to helium gas prodiietion from the decay of actinide nuclides in the waste may produce sufficient strain to induce cracking of the glass. However, cracking may be avoided by fabricating waste glasses in the form of spheres less than about 8 cm in diameter. (auth)

Physical Description

Pages: 53

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Dep. NTIS

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  • Other Information: Orig. Receipt Date: 30-JUN-74

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  • Report No.: BNWL--1788
  • Grant Number: AT(45-1)-1830
  • DOI: 10.2172/4408896 | External Link
  • Office of Scientific & Technical Information Report Number: 4408896
  • Archival Resource Key: ark:/67531/metadc1022619

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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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  • October 1, 1973

Added to The UNT Digital Library

  • Oct. 15, 2017, 10:09 p.m.

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  • Feb. 1, 2018, 1:58 p.m.

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Platt, A. M. Research and development activities, waste fixation program. Quarterly progress report, July--September 1973, report, October 1, 1973; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc1022619/: accessed November 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.