Zobrazeno 1 - 10
of 26
pro vyhledávání: '"D.W. Faletti"'
Autor:
L.J. Ethridge, D.W. Faletti
Publikováno v:
Nuclear and Chemical Waste Management. 8:123-133
The radioactive liquid-fed ceramic melter technology is being implemented in the United States and abroad for the disposal of high-level radioactive wastes by vitrification. The resulting glass is poured into metal canisters. Thermal gradients develo
Autor:
C.R. Allen, S.O. Bates, R.D. Dierks, H.C. Burkholder, R.D. Peters, M.E. Peterson, R.W. Goles, B.A. Pulsipher, C.M. Andersen, W.L. Kuhn, R.K. Farnsworth, P.W. Reimus, D.W. Faletti, Nakaoka, R.K.: Perez, J.M
Individual papers are processed separately for the data bases. This report documents progress on liquid-fed ceramic melter (LFCM) vitrification technology. Progress in melting process chemistry and glass development, feed preparation and transfer sys
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2127a3e6a29b085f52597b69abd14aae
https://doi.org/10.2172/5917891
https://doi.org/10.2172/5917891
Autor:
R.A. Brouns, C.R. Allen, J.A. Powell, S.O. Bates, L.A. Bray, M.J. Budden, R.D. Dierks, M.L. Elliott, M.R. Elmore, D.W. Faletti, R.K. Farnsworth, L.K. Jr. Holton, W.L. Kuhn, G.B. Mellinger, R.K. Nakaoka, M.E. Peterson, G.F. Piepel, B.A. Pulsipher, M.A.H. Reimus, J.E. Surma, K.D. Wiemers
This report describes the progress in developing, testing, applying and documenting liquid-fed ceramic melter vitrification technology. Progress in the following technical subject areas during the fourth quarter of FY 1987 is discussed: melting proce
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0d295dc3429c762f74af81315a40ab30
https://doi.org/10.2172/7025660
https://doi.org/10.2172/7025660
Pacific Northwest Laboratory (PNL) researchers used the TEMPEST computer code to simulate thermal cooldown behavior of nuclear waste glass after it was poured into steel canisters for long-term storage. The objective of this work was to determine the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2331674756fcaf6f84414f68a507817c
https://doi.org/10.2172/6960737
https://doi.org/10.2172/6960737
Experiments were performed to assess the operating characteristics and potential performance of water-augmented dry cooling systems. The work was aimed at evaluating a deluged air-cooled HOETERV plate fin heat exchanger surface proposed for integrate
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::644cc65950a65eb77676abcfd60c4a75
https://doi.org/10.2172/5984126
https://doi.org/10.2172/5984126
The RECIPE code was developed by Pacific Northwest Laboratory under the West Valley Support Task of the Nuclear Waste Treatment Program. Additional chemicals must be added to the high-level wastes to produce an acceptable glass. To maintain the compo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f446c701b5442c0991571e5209b65475
https://doi.org/10.2172/5492798
https://doi.org/10.2172/5492798
Results of a detailed engineering and cost study of three different all-dry cooling systems to assess the potential for reducing the cost of all-dry cooling for steam electric power plants are described. The three types of cooling systems considered
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::50723429849ff2f662d405255961485c
https://doi.org/10.2172/7257558
https://doi.org/10.2172/7257558
This appendix to User's Manual for the BNW-1 Optimization Code for Dry-Cooled Power Plants provides a listing of the BNW-I optimization code for determining, for a particular size power plant, the optimum dry cooling tower design using a plastic tube
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0d6fde68abde72bc43d53e5599d09280
https://doi.org/10.2172/7280118
https://doi.org/10.2172/7280118