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020 _a9783319236513
040 _aES-MaUEC
050 4 _aTA434
_b.O247 2016
082 0 4 _a620.11
100 1 _aOchs, Michael.
_997544
_0Local
245 1 0 _aRadionuclide and Metal Sorption on Cement and Concrete
_cby Michael Ochs, Dirk Mallants, Lian Wang
250 _a1st ed.
260 _aCham
_bSpringer International Publishing
_c2016
300 _a1 recurso en línea (XXX, 301 páginas) :
336 _aTexto
_btxt
_2rdacontent
337 _aelectrónico
_bc
_2rdamedia
338 _arecurso electrónico
_bcr
_2rdacarrier
490 0 _aTopics in Safety, Risk, Reliability and Quality
_x1566-0443
_v9999
505 0 _a1 Introduction and objective -- 2 Cementitious materials and their sorption properties -- 3 Sorption values for chlorine and iodine -- 4 Sorption values for caesium, strontium, radium and silver -- 5 Sorption values for calcium, nickel and carbon -- 6 Sorption values for thorium, uranium, plutonium, neptunium and protactinium -- 7 Sorption values for americium -- 8 Sorption values for selenium, molybdenum and technetium -- 9 Sorption values for palladium and lead -- 10 Sorption values for niobium and tin -- 11 Sorption values for hydrogen and beryllium -- 12 Sorption values for zirconium -- Annex Summary tables with sorption data. ��.
520 3 _aCementitious materials are being widely used as solidification/stabilisation and barrier materials for a variety of chemical and radioactive wastes, primarily due to their favourable retention properties for metals, radionuclides and other contaminants. The retention properties result from various mineral phases in hydrated cement that possess a high density and diversity of reactive sites for the fixation of contaminants through a variety of sorption and incorporation reactions. This book presents a state of the art review and critical evaluation of the type and magnitude of the various sorption and incorporation processes in hydrated cement systems for twenty-five elements relevant for a broad range of radioactive and industrial wastes. Effects of cement evolution or ageing on sorption/incorporation processes are explicitly evaluated and quantified. While the immobilisation of contaminants by mixing-in during hydration is not explicitly addressed, the underlying chemical processes are similar. A quantitative database on the solid/liquid distribution behaviour of radionuclides and other elements in hydrated cement systems is established on the basis of a consistent review and re-evaluation of literature data. In addition to recommended values, all underlying original experimental data and key experimental info rmation are provided, which allows users to trace the given recommendations or to develop their own set of key values. This database is closely tied to the safety analysis of near surface disposal of radioactive waste in Belgium. It focuses on radioelements, toxic stable elements and heavy metals, which makes it relevant for investigations involving the interaction of radioactive and conventional contaminants with cement-based barriers.
710 2 _aSpringerLink (Online service)
_0Local
_9106996
942 _2lcc
_cLE
988 _aEBOOK, asignarmaterias , EBSPRINGER
650 0 7 _aMateriales
_0
_2embne
_9138253
650 7 _9139804
_aTermodinámica
_0comprobar BNE19900977115
_2embne
700 1 _aMallants, Dirk.
_997545
_0Local
700 1 _aWang, Lian.
_997546
_0Local
856 4 0 _uhttps://go.openathens.net/redirector/universidadeuropea.es?url=https://link.springer.com/book/10.1007/978-3-319-23651-3
_zAcceso a este recurso digital (usuarios Universidad Europea de Madrid)
901 _ai9783319236513
907 _a.b12942297
_b10-10-17
_c21-11-16
998 _am
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