Zobrazeno 1 - 10
of 21
pro vyhledávání: '"R.A. Brouns"'
Publikováno v:
Nuclear and Chemical Waste Management. 4:267-276
Pacific Northwest Laboratory (PNL) is developing in situ vitrification (ISV) as an in-place stabilization technique for buried radioactive and hazardous chemical wastes. The process melts the wastes and surrounding soil to produce a durable glass and
Autor:
R.A. Brouns, C.T. Li
A process was investigated to remove hydrogen sulfide (H{sub2}S) from geothermal steam. This process is an upstream steam treatment process which utilizes a catalytic oxidation reaction to convert H{sub2}S in geothermal steam to water vapor and sulfu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::114b2e17082029794171a0798ce96470
https://doi.org/10.2172/6161336
https://doi.org/10.2172/6161336
To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management sy
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ffdad90c380924fdcbd88bf97f7a042b
https://doi.org/10.2172/5598580
https://doi.org/10.2172/5598580
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
Scoping studies have been performed at the Pacific Northwest Laboratory related to the direct liquid-feeding of a generic high-level defense waste to a joule-heated ceramic melter. Tests beginning on the laboratory scale and progressing to full-scale
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b486b1deafab9b7a371f57f3ad3a12a3
https://doi.org/10.2172/7046946
https://doi.org/10.2172/7046946
This report is compiled by the Nuclear Waste treatment Program and the Hanford Waste Vitrification Program at Pacific Northwest Laboratory to describe the progress in developing, testing, applying and documenting liquid-fed ceramic melter vitrificati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1345b8ac5bba47f7ef8e12649bc8fe6c
https://doi.org/10.2172/6883013
https://doi.org/10.2172/6883013
Autor:
C.C. Chapman, R.A. Brouns, S.M. Barnes, R.D. Peters, D.H. Siemens, M. M. Beary, R.M. Jones, D.N. Berger, M.E. Peterson
A liquid-fed joule-heated ceramic melter system is the reference process for immobilization of the high-level liquid waste in the US and several foreign countries. This system has been under development for over ten years at Pacific Northwest Laborat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::afe4aead5e676bd4c4b900b6d5046c14
https://doi.org/10.2172/5864310
https://doi.org/10.2172/5864310
Autor:
R.A. Brouns, J.A. Powell
Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a4817cd9b3e4ae332755860f929300b7
https://doi.org/10.2172/6817496
https://doi.org/10.2172/6817496