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Cementitious Materials for Nuclear Waste Immobilization [Kõva köide]

  • Formaat: Hardback, 248 pages, kõrgus x laius x paksus: 252x178x18 mm, kaal: 535 g
  • Ilmumisaeg: 14-Nov-2014
  • Kirjastus: John Wiley & Sons Inc
  • ISBN-10: 1118512006
  • ISBN-13: 9781118512005
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  • Formaat: Hardback, 248 pages, kõrgus x laius x paksus: 252x178x18 mm, kaal: 535 g
  • Ilmumisaeg: 14-Nov-2014
  • Kirjastus: John Wiley & Sons Inc
  • ISBN-10: 1118512006
  • ISBN-13: 9781118512005
Teised raamatud teemal:
Cementitious materials are an essential part in any radioactive waste disposal facility. Conditioning processes such as cementation are used to convert waste into a stable solid form that is insoluble and will prevent dispersion to the surrounding environment. It is incredibly important to understand the long-term behavior of these materials. This book summarises approaches and current practices in use of cementitious materials for nuclear waste immobilisation. It gives a unique description of the most important aspects of cements as nuclear waste forms: starting with a description of wastes, analyzing the cementitious systems used for immobilization and describing the technologies used, and ending with analysis of cementitious waste forms and their long term behavior in an envisaged disposal environment.

Extensive research has been devoted to study the feasibility of using cement or cement based materials in immobilizing and solidifying different radioactive wastes. However, these research results are scattered. This work provides the reader with both the science and technology of the immobilization process, and the cementitious materials used to immobilize nuclear waste. It summarizes current knowledge in the field, and highlights important areas that need more investigation.

The chapters include: Introduction, Portland cement, Alternative cements, Cement characterization and testing, Radioactive waste cementation, Waste cementation technology, Cementitious wasteform durability and performance assessment.
About the Authors xi
Preface xiii
1 Introduction
1(26)
1.1 Background of Nuclear Waste Problem
1(1)
1.2 Nuclear Industry Facilities
2(8)
1.2.1 NFC Facilities
2(6)
1.2.2 Radioisotope Production and Application
8(2)
1.3 Nuclear Waste Sources and Classification
10(3)
1.4 Nuclear Waste Management
13(10)
1.4.1 Development of Policy Principles, Strategy and Legal Framework
14(2)
1.4.2 Technical Options for a Waste Management System
16(6)
1.4.3 Technical Factors that Affect Technology Selection
22(1)
1.5 Wasteform Materials
23(4)
References
25(2)
2 Cements: Portland Cement
27(26)
2.1 Cements
27(1)
2.2 Portland Cement: Manufacture, Mineral Composition, Properties
28(2)
2.3 Phase and Mineral Composition of Ordinary Portland Cement
30(1)
2.4 Properties of Portland Cement
31(1)
2.5 Hydration of Portland Cement
32(12)
2.5.1 Hydration and Hydraulic Activity of Clinker Phases and Portland Cement
32(3)
2.5.2 Process Chemistry, Products and Hydration Stages
35(5)
2.5.3 Microstructure, Phases and Properties of Fresh and Hardened Cement Paste
40(4)
2.6 Interaction of Portland Cements with Water and Soil
44(9)
2.6.1 Ground Waters and Their Interaction with Cement Hydration Products
44(4)
2.6.2 Soil and Its Interaction with Cement Hydration Products
48(3)
References
51(2)
3 Portland Cements with Mineral and Chemical Admixtures
53(26)
3.1 Chemical Admixtures to Control the Structure and Properties of Portland Cements
53(8)
3.1.1 Accelerators
55(1)
3.1.2 Retarders
56(1)
3.1.3 Plasticizers, Super-Plasticizers and Hyperplasticizers
57(4)
3.2 Mineral Admixtures in the Control of the Composition, Structure and Properties of Cements
61(18)
3.2.1 Classification of Mineral Admixtures for Cements
62(4)
3.2.2 Portland Cements with Mineral Admixtures from Natural Rocks and Minerals
66(1)
3.2.3 Portland Cements with Mineral Admixtures from Wastes of Various Industries
67(2)
3.2.4 Portland Cements with Synthetic Mineral Admixtures
69(1)
3.2.5 Portland Cements with Hybrid Mineral and Organic-Mineral Admixtures
70(4)
References
74(5)
4 Alternative Binders
79(26)
4.1 Calcium Aluminate Cements
80(3)
4.1.1 Chemical and Mineralogical Composition of CACs
80(1)
4.1.2 Hardening of CACs
81(1)
4.1.3 Properties of CACs
82(1)
4.2 Calcium Sulphoaluminate Cements
83(4)
4.2.1 Chemical and Mineralogical Composition of CSACs
84(1)
4.2.2 Hardening of CSACs
84(2)
4.2.3 Properties of CSACs
86(1)
4.3 Phosphate Cements
87(5)
4.3.1 Properties of Phosphate Cements
89(1)
4.3.2 Magnesium Phosphate Cements
90(1)
4.3.3 Calcium Phosphate Cements
90(2)
4.4 Alkali-Activated Cements
92(13)
References
99(6)
5 Cement Properties, Characterization and Testing
105(22)
5.1 Water/Cement Ratio, Water Requirement, Workability and Water Retention
105(4)
5.2 Setting Time
109(2)
5.3 Specific Surface Area and Particle Size Distribution
111(2)
5.4 Heat Evolution
113(1)
5.5 Strength
114(5)
5.6 Freeze---Thaw Resistance
119(2)
5.7 Microstructure and Analysis
121(6)
References
124(3)
6 Radioactive Waste Cementation
127(32)
6.1 Radioactive Waste Streams for Cementation
127(3)
6.2 Liquid Waste
130(8)
6.2.1 Organic Liquid Waste for Cementation
130(2)
6.2.2 Aqueous Waste for Cementation
132(6)
6.3 Bulk Solid Radioactive Wastes
138(5)
6.3.1 Bulk Metallic Wastes
138(2)
6.3.2 Bulk Concrete Wastes
140(2)
6.3.3 Bulk Graphite
142(1)
6.3.4 Bulk Hazardous Wastes
143(1)
6.4 Fragmented (Dispersed) Solid Wastes
143(4)
6.4.1 Compactable, Combustible Wastes
144(1)
6.4.2 Non-compactable, Non-combustible Wastes
145(2)
6.5 Additives for Radioactive Waste Cementation
147(5)
6.5.1 Lime
148(1)
6.5.2 Blast Furnace Slag
149(1)
6.5.3 Clay Minerals
149(3)
6.6 Cement-Based Composite Materials
152(1)
6.7 Cement-Based Wasteform Optimization
153(6)
References
154(5)
7 Waste Cementation Technology
159(18)
7.1 Methods of Liquid Waste Cementation
159(9)
7.1.1 Regular Mixer Technology
161(2)
7.1.2 Disposable Stirrer Technology
163(4)
7.1.3 Slant Mixer Technology
167(1)
7.1.4 High Energy and High Shear Mixer Technology
168(1)
7.1.5 In-line Mixing Technology
168(1)
7.2 Methods for Cementation of Fragmented (Dispersed) Solid Waste
168(5)
7.3 Methods for Cementation of Bulk Solid Waste
173(1)
7.4 Quality Control of Technological Processes and Materials Obtained
174(3)
References
175(2)
8 Cementitious Wasteform Durability
177(24)
8.1 Wasteform Durability Requirements
177(4)
8.2 Role of Material Performance
181(1)
8.3 Expected Performance of Cements
182(3)
8.4 Wasteform Leaching Parameters
185(1)
8.5 Laboratory Tests
186(2)
8.6 Long-Term Field Tests
188(7)
8.6.1 Mound Type Repository Field Tests
189(5)
8.6.2 Vault Repository Field Tests
194(1)
8.7 Effect of Radiation
195(1)
8.8 Biological Effects
196(1)
8.9 Role of Filling Materials
197(4)
References
198(3)
9 Performance Assessment
201(20)
9.1 Historical Disposal Practice
202(2)
9.2 Disposal Facility Design
204(6)
9.2.1 Shallow Land Disposal Options
206(2)
9.2.2 Underground Disposal Option
208(2)
9.3 Modelling Approaches
210(2)
9.4 Performance Assessment
212(4)
9.5 Safety Case
216(5)
References
217(4)
10 Future Trends and Concluding Remarks
221(6)
10.1 Role of Cementitious Materials
221(1)
10.2 Novel Cementitious Materials
222(2)
10.3 Concluding Remarks
224(3)
References
225(2)
Index 227
Rehab O. Abdel Rahman is Nuclear Engineering Lecturer, at the Atomic Energy Authority of Egypt, Cairo, Egypt. He has been working in the field of nuclear engineering for almost 20 years, and has published in several international journals. His areas of research include radioactive waste management: performance assessment, material selection, cementitious material.

Ravil Z. Rakhimov and Nailia R. Rakhimova are Professor and Assistant Professor at Kazan State University of Architecture and Engineering, Russian Federation.  Ravil has almost forty years experience of teaching in the fields of materials science and cementitious materials. He is the author of more than 35 patents, 29 monographs and textbooks and nearly 600 papers in Russian. Current research interests include building material science and cementitious materials. Nailia has fifteen years experience in materials science, and mineral binders. She holds 6 patents, has written one monograph and more than100 papers, mostly in Russian.

Michael Ojovan is Assistant Professor at the University of Sheffield, Visiting Professor at Imperial College, London, and Nuclear Engineer at the International Atomic Energy Agency (IAEA), Austria. Prior to this he spent he 20 years at The Moscow Scientific and Industrial Association "Radon", the leading radioactive waste research institution of Russian Federation. He is a Fellow of Russian Academy of Natural Sciences and a Technical Expert of the International Atomic Energy Agency. He has published over 290 peer reviewed scientific papers, 6 books on nuclear materials, 6 book chapters, 14 IAEA documents and has 42 patents. He has also been awarded research grants totalling over £7M.