Research and development activities: high-level waste immobilization program. Quarterly progress report, January-March 1979

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Liquid waste, made from zirconium-clad UO/sub 2/ power reactor fuel with an average burnup of 25,000 MWd/MT, was converted to glass by the in-can melting process. An intrinsic-gamma melt-level detection system was tested during the NWVP demonstrations; results showed that if a sufficient number of collimators are used the system will track the melt surface with a precision of 1 in. during the filling of cans with waste glass. The two canisters filled in the NWVP are both 8 in. in diameter and contain borosilicate glass of very similar compositions. One canister contains 116 kg of glass that generated 0.38 ... continued below

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Pages: 50

Creation Information

McElroy, J.L.; Mendel, J.E.; Bonner, W.F. & Henry, M.H. November 1, 1979.

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

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Description

Liquid waste, made from zirconium-clad UO/sub 2/ power reactor fuel with an average burnup of 25,000 MWd/MT, was converted to glass by the in-can melting process. An intrinsic-gamma melt-level detection system was tested during the NWVP demonstrations; results showed that if a sufficient number of collimators are used the system will track the melt surface with a precision of 1 in. during the filling of cans with waste glass. The two canisters filled in the NWVP are both 8 in. in diameter and contain borosilicate glass of very similar compositions. One canister contains 116 kg of glass that generated 0.38 kW of self-heat when produced; the other contains 145 kg of glass, and generates 1.01 kW. Spray calcination of simulated Savannah River Plant liquid waste at a rate of 400 L/h was demonstrated in the 36-in.-dia. calciner. Five waste forms are being compared: concrete-containing waste calcine, sintered waste glass, glass-ceramic, Synroc B (a crystalline assemblage of titanates), and borosilicate waste glass (composition 76-68). Results of initial tests indicate that the reaction rate of carbon with water, previously found to be very low, may be increased in a radiation field.

Physical Description

Pages: 50

Notes

Dep. NTIS, PC A03/MF A01.

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  • Report No.: PNL-3050-1
  • Grant Number: EY-76-C-06-1830
  • DOI: 10.2172/5602199 | External Link
  • Office of Scientific & Technical Information Report Number: 5602199
  • Archival Resource Key: ark:/67531/metadc1092972

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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

  • November 1, 1979

Added to The UNT Digital Library

  • Feb. 10, 2018, 10:06 p.m.

Description Last Updated

  • April 19, 2018, 7:12 p.m.

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McElroy, J.L.; Mendel, J.E.; Bonner, W.F. & Henry, M.H. Research and development activities: high-level waste immobilization program. Quarterly progress report, January-March 1979, report, November 1, 1979; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc1092972/: accessed September 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.