{"product_id":"nuclear-materials-under-irradiation-hardback-9781789451481","title":"Nuclear Materials Under Irradiation (Hardback) 9781789451481","description":"\u003cfont face=\"Georgia\"\u003e\r\n\u003cp\u003e\u003cfont size=\"6\"\u003eNuclear Materials Under Irradiation\u003c\/font\u003e\u003cbr\u003e\r\n\r\n\r\n\r\n\r\n\r\n\u003c\/p\u003e\n\u003cp\u003e\u003cfont size=\"4\"\u003eSerge Bouffard (Edited by), Bouffard (Author), Nathalie Moncoffre (Edited by)\u003c\/font\u003e\u003c\/p\u003e\r\n\r\n\u003cp\u003e\u003cfont size=\"3\"\u003e9781789451481, Wiley\u003c\/font\u003e\u003c\/p\u003e\r\n\r\n\u003cp\u003e\u003cfont size=\"3\"\u003eHardback, published 13 December 2023\u003c\/font\u003e\u003c\/p\u003e\r\n\r\n\u003cp\u003e\u003cfont size=\"3\"\u003e320 pages\u003cbr\u003e23.5 x 15.6 x 2 cm, 0.717 kg\u003c\/font\u003e\u003c\/p\u003e\r\n\r\n\r\n\r\n\r\n\r\n\u003cp align=\"justify\"\u003e\u003cstrong\u003e\u003cfont size=\"3\"\u003e\u003cp\u003eAt every stage of the fuel cycle, the materials used are at the heart of nuclear energy safety issues. These materials, which range from steel to polymers, including ceramics, glass, concrete and graphite, are submitted to extreme stresses combining mechanical, thermal and irradiation constraints.\u003c\/p\u003e \u003cp\u003eThe objective of this book is to provide a basis for the research of nuclear materials subjected to irradiation, with the desire to contextualize them in the industrial environment. Therefore, most of the chapters are co-authored and contain a mix of basic and applied research. The reader will find chapters on nuclear reactor materials (structural materials, neutron absorbers, moderators and nuclear fuel) and on materials in waste management (glass, concrete and organic materials). These material chapters are complemented by more general information on defects and their creation, radiolysis and irradiation and characterization tools.\u003c\/p\u003e\u003c\/font\u003e\u003c\/strong\u003e\u003c\/p\u003e\r\n\r\n\u003cp\u003e\u003cfont size=\"3\"\u003e\u003cp\u003ePreface xi\u003cbr\u003e \u003ci\u003eSerge Bouffard and Nathalie Moncoffre\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e\u003cb\u003eChapter 1 Irradiation Defects 1\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eSerge Bouffard and David Siméone\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e1.1 Introduction 1\u003c\/p\u003e \u003cp\u003e1.2 Some basic data 2\u003c\/p\u003e \u003cp\u003e1.2.1 Radiative environments and nuclear materials 2\u003c\/p\u003e \u003cp\u003e1.2.2 Some notions about the transport of particles in matter 5\u003c\/p\u003e \u003cp\u003e1.2.3 The zoology of irradiation defects 9\u003c\/p\u003e \u003cp\u003e1.3 Defect creation mechanisms 11\u003c\/p\u003e \u003cp\u003e1.3.1 Creation of defects by elastic collisions 13\u003c\/p\u003e \u003cp\u003e1.3.2 Amorphization 16\u003c\/p\u003e \u003cp\u003e1.3.3 Creation of defects by electronic excitation 18\u003c\/p\u003e \u003cp\u003e1.3.4 Synergy between elastic collisions and electronic excitations 26\u003c\/p\u003e \u003cp\u003e1.4 Kinetics of defect evolution 28\u003c\/p\u003e \u003cp\u003e1.4.1 Mean field approach: reaction rate theory 29\u003c\/p\u003e \u003cp\u003e1.4.2 Evolution of extended defects: kinetics of clusters in the mean field 33\u003c\/p\u003e \u003cp\u003e1.4.3 Kinetic Monte Carlo approach 34\u003c\/p\u003e \u003cp\u003e1.4.4 Phase field approach 36\u003c\/p\u003e \u003cp\u003e1.5 Open-ended problems 38\u003c\/p\u003e \u003cp\u003e1.6 Acknowledgements 40\u003c\/p\u003e \u003cp\u003e1.7 References 40\u003c\/p\u003e \u003cp\u003e\u003cb\u003eChapter 2 Metal Alloys 47\u003cbr\u003e \u003c\/b\u003e\u003ci\u003ePhilippe Pareige and Christophe Domain\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e2.1 Introduction 47\u003c\/p\u003e \u003cp\u003e2.2 Fuel cladding 52\u003c\/p\u003e \u003cp\u003e2.2.1 Growth and creep under irradiation 54\u003c\/p\u003e \u003cp\u003e2.2.2 Stress corrosion cracking 56\u003c\/p\u003e \u003cp\u003e2.2.3 The mechanisms of the evolution of the properties under irradiation 57\u003c\/p\u003e \u003cp\u003e2.2.4 Simulations of growth and creep under irradiation 58\u003c\/p\u003e \u003cp\u003e2.3 Internal structures in austenitic steel 59\u003c\/p\u003e \u003cp\u003e2.3.1 An effect of irradiation: intergranular segregation 61\u003c\/p\u003e \u003cp\u003e2.3.2 Evolution of mechanical properties under irradiation 64\u003c\/p\u003e \u003cp\u003e2.3.3 Creep under irradiation 65\u003c\/p\u003e \u003cp\u003e2.3.4 Swelling 66\u003c\/p\u003e \u003cp\u003e2.3.5 Irradiation-assisted stress corrosion cracking 67\u003c\/p\u003e \u003cp\u003e2.4 The vessel 69\u003c\/p\u003e \u003cp\u003e2.4.1 Changes in tenacity and resilience 70\u003c\/p\u003e \u003cp\u003e2.4.2 Cluster dynamics 72\u003c\/p\u003e \u003cp\u003e2.5 Perspectives 77\u003c\/p\u003e \u003cp\u003e2.6 References 80\u003c\/p\u003e \u003cp\u003e\u003cb\u003eChapter 3 Ceramics within PWRs 87\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eChristine Delafoy, Frederico Garrido and Yves Pipon\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e3.1 Introduction 87\u003c\/p\u003e \u003cp\u003e3.2 Development and typical properties of UO\u003csub\u003e2\u003c\/sub\u003e and B\u003csub\u003e4\u003c\/sub\u003eC ceramics 91\u003c\/p\u003e \u003cp\u003e3.2.1 Development and structure of uranium dioxide 91\u003c\/p\u003e \u003cp\u003e3.2.2 Development and structure of boron carbide 93\u003c\/p\u003e \u003cp\u003e3.2.3 Thermomechanical characteristics of B\u003csub\u003e4\u003c\/sub\u003eC and UO\u003csub\u003e2\u003c\/sub\u003e 96\u003c\/p\u003e \u003cp\u003e3.3 Aging of ceramics under irradiation 100\u003c\/p\u003e \u003cp\u003e3.3.1 Evolution of the properties of uranium dioxide under irradiation 101\u003c\/p\u003e \u003cp\u003e3.3.2 Evolution of boron carbide properties under irradiation 112\u003c\/p\u003e \u003cp\u003e3.4 Future challenges 116\u003c\/p\u003e \u003cp\u003e3.5 References 120\u003c\/p\u003e \u003cp\u003e\u003cb\u003eChapter 4 Nuclear Graphite 125\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eNicolas Bérerd and Laurent Petit\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e4.1 What is nuclear graphite? 125\u003c\/p\u003e \u003cp\u003e4.2 Why use graphite in nuclear reactors? 128\u003c\/p\u003e \u003cp\u003e4.3 Evolution of nuclear graphite in reactors 129\u003c\/p\u003e \u003cp\u003e4.3.1 Neutron irradiation 130\u003c\/p\u003e \u003cp\u003e4.3.2 Irradiation defects in nuclear graphite 133\u003c\/p\u003e \u003cp\u003e4.3.3 Evolution of lattice parameters and crystallite size in irradiated graphite 139\u003c\/p\u003e \u003cp\u003e4.3.4 Density and porosity evolution by radiolytic corrosion of graphite 141\u003c\/p\u003e \u003cp\u003e4.3.5 What are the consequences at the macroscopic scale? 142\u003c\/p\u003e \u003cp\u003e4.4 Conclusion 143\u003c\/p\u003e \u003cp\u003e4.5 Acknowledgements 144\u003c\/p\u003e \u003cp\u003e4.6 References 145\u003c\/p\u003e \u003cp\u003e\u003cb\u003eChapter 5 Nuclear Glasses 151\u003c\/b\u003e\u003c\/p\u003e \u003cp\u003eMagaly Tribet\u003c\/p\u003e \u003cp\u003e5.1 Glass of nuclear interest: their role and their aging conditions under irradiation 151\u003c\/p\u003e \u003cp\u003e5.1.1 What is this kind of glass for? 151\u003c\/p\u003e \u003cp\u003e5.1.2 What does this glass actually contain and in what form? 152\u003c\/p\u003e \u003cp\u003e5.1.3 Nuclear glass radioactivity 154\u003c\/p\u003e \u003cp\u003e5.1.4 A complex scenario of glass aging under deep geological conditions 157\u003c\/p\u003e \u003cp\u003e5.2. How are the effects of long-term irradiation studied at the laboratory scale? 158\u003c\/p\u003e \u003cp\u003e5.3 Closed system: evolution of glass subjected to its self-irradiation and to the accumulation of helium 161\u003c\/p\u003e \u003cp\u003e5.3.1 Impact of βγ irradiation 161\u003c\/p\u003e \u003cp\u003e5.3.2 Effects of α decays 163\u003c\/p\u003e \u003cp\u003e5.3.3 Accumulation of helium 165\u003c\/p\u003e \u003cp\u003e5.3.4 Summary of knowledge in closed system 166\u003c\/p\u003e \u003cp\u003e5.4 Open system: alteration of glass by water under irradiation 167\u003c\/p\u003e \u003cp\u003e5.4.1 General information on the behavior of glass under water – methodology 167\u003c\/p\u003e \u003cp\u003e5.4.2 Taking irradiation into account in this multi-phase system 170\u003c\/p\u003e \u003cp\u003e5.4.3 Irradiation and initial alteration rate 170\u003c\/p\u003e \u003cp\u003e5.4.4 Irradiation and residual alteration rate 172\u003c\/p\u003e \u003cp\u003e5.4.5 Summary on the behavior of glass under water and under irradiation 174\u003c\/p\u003e \u003cp\u003e5.5 Summary and prospects 175\u003c\/p\u003e \u003cp\u003e5.6 Acknowledgements 176\u003c\/p\u003e \u003cp\u003e5.7 References 176\u003c\/p\u003e \u003cp\u003e\u003cb\u003eChapter 6 Radiolysis of Porous Materials and Radiolysis at Interfaces 181\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eSophie Le Caër and Jean-Philippe Renault\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e6.1 Introduction 181\u003c\/p\u003e \u003cp\u003e6.2 General information on radiolysis 182\u003c\/p\u003e \u003cp\u003e6.2.1 A few definitions 182\u003c\/p\u003e \u003cp\u003e6.2.2 Radiolysis of liquid water 183\u003c\/p\u003e \u003cp\u003e6.3 Main porous materials of interest 185\u003c\/p\u003e \u003cp\u003e6.4 Dosimetry in heterogeneous media 186\u003c\/p\u003e \u003cp\u003e6.5 Production of dihydrogen by radiolysis of water in a confined medium 187\u003c\/p\u003e \u003cp\u003e6.5.1 Methods for calculating the yield of dihydrogen production 187\u003c\/p\u003e \u003cp\u003e6.5.2 Reaction mechanisms 189\u003c\/p\u003e \u003cp\u003e6.5.3 Different parameters influencing the production of dihydrogen under irradiation 190\u003c\/p\u003e \u003cp\u003e6.6 Understanding transient phenomena 191\u003c\/p\u003e \u003cp\u003e6.6.1 Study of a short-lived species, the hydroxyl radical 191\u003c\/p\u003e \u003cp\u003e6.6.2 Confinement effect on the reactions taking place and their rate constants 193\u003c\/p\u003e \u003cp\u003e6.7 Conclusion: what about the effects of radiolytic species on materials? 196\u003c\/p\u003e \u003cp\u003e6.8 References 197\u003c\/p\u003e \u003cp\u003e\u003cb\u003eChapter 7 Concrete and Cement Materials under Irradiation 201\u003cbr\u003e \u003c\/b\u003e\u003ci\u003ePascal Bouniol\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e7.1 Introduction 201\u003c\/p\u003e \u003cp\u003e7.2 Radiation shielding concrete 202\u003c\/p\u003e \u003cp\u003e7.2.1 Overview 202\u003c\/p\u003e \u003cp\u003e7.2.2 Effects of irradiation on the cement matrix 203\u003c\/p\u003e \u003cp\u003e7.2.3 Effects of irradiation on aggregates 204\u003c\/p\u003e \u003cp\u003e7.2.4 Prediction of concrete damage 206\u003c\/p\u003e \u003cp\u003e7.3 Waste conditioning matrices 207\u003c\/p\u003e \u003cp\u003e7.3.1 Overview 207\u003c\/p\u003e \u003cp\u003e7.3.2 Radiolysis of the cement matrix 207\u003c\/p\u003e \u003cp\u003e7.3.3 Phenomenological couplings 210\u003c\/p\u003e \u003cp\u003e7.4 Conclusion 211\u003c\/p\u003e \u003cp\u003e7.5 References 212\u003c\/p\u003e \u003cp\u003e\u003cb\u003eChapter 8 Organic Materials 215\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eEmmanuel Balanzat and Muriel Ferry\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e8.1 Introduction 215\u003c\/p\u003e \u003cp\u003e8.2 Technological context 217\u003c\/p\u003e \u003cp\u003e8.2.1 Organic materials of the nuclear industry 217\u003c\/p\u003e \u003cp\u003e8.2.2 Polymers in the reactor building 220\u003c\/p\u003e \u003cp\u003e8.2.3 Nuclear waste 222\u003c\/p\u003e \u003cp\u003e8.3 Radiation exposure 224\u003c\/p\u003e \u003cp\u003e8.3.1 The LET effect 224\u003c\/p\u003e \u003cp\u003e8.3.2 β\/γ irradiation 225\u003c\/p\u003e \u003cp\u003e8.3.3 α irradiation 225\u003c\/p\u003e \u003cp\u003e8.3.4 Thermal neutrons 227\u003c\/p\u003e \u003cp\u003e8.3.5 Other projectiles 227\u003c\/p\u003e \u003cp\u003e8.4 Irradiated polymers: phenomenology 228\u003c\/p\u003e \u003cp\u003e8.4.1 Resistance of polymers to irradiation 228\u003c\/p\u003e \u003cp\u003e8.4.2 Changes induced by irradiation 230\u003c\/p\u003e \u003cp\u003e8.5 Radiolysis in anoxic polymers: fundamental effects 231\u003c\/p\u003e \u003cp\u003e8.5.1 Polymer radiolysis: introduction 231\u003c\/p\u003e \u003cp\u003e8.5.2 A textbook case: polyethylene 233\u003c\/p\u003e \u003cp\u003e8.6 The radio-oxidation of polymers 236\u003c\/p\u003e \u003cp\u003e8.6.1 Mechanism of radio-oxidation 236\u003c\/p\u003e \u003cp\u003e8.6.2 Chemical and physical influences of the dose rate 239\u003c\/p\u003e \u003cp\u003e8.6.3 α irradiation 241\u003c\/p\u003e \u003cp\u003e8.7 Conclusion and perspectives 243\u003c\/p\u003e \u003cp\u003e8.8 References 243\u003c\/p\u003e \u003cp\u003e\u003cb\u003eChapter 9 Irradiation Tools 251\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eSerge Bouffard and Nathalie Moncoffre\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e9.1 Why experiment with accelerators? 251\u003c\/p\u003e \u003cp\u003e9.2 Irradiation conditions in nuclear energy 252\u003c\/p\u003e \u003cp\u003e9.2.1 Characteristics of these particles 252\u003c\/p\u003e \u003cp\u003e9.2.2 How is irradiation simulated in a nuclear environment? 253\u003c\/p\u003e \u003cp\u003e9.3 Tools for simulation 256\u003c\/p\u003e \u003cp\u003e9.3.1 Research reactors 256\u003c\/p\u003e \u003cp\u003e9.3.2 Accelerators 258\u003c\/p\u003e \u003cp\u003e9.3.3 Use of radioactive elements 264\u003c\/p\u003e \u003cp\u003e9.4 Some major irradiation research centers 264\u003c\/p\u003e \u003cp\u003e9.5 Conclusion 267\u003c\/p\u003e \u003cp\u003e9.6 References 267\u003c\/p\u003e \u003cp\u003e\u003cb\u003eChapter 10 Characterization of Irradiation Damage 269\u003cbr\u003e \u003c\/b\u003e\u003ci\u003eAurélie Gentils, Stéphanie Jublot-Leclerc and Patrick Simon\u003c\/i\u003e\u003c\/p\u003e \u003cp\u003e10.1 Introduction 269\u003c\/p\u003e \u003cp\u003e10.2 Characterization of point defects 270\u003c\/p\u003e \u003cp\u003e10.2.1 Positron annihilation spectroscopy 270\u003c\/p\u003e \u003cp\u003e10.2.2 Raman scattering 271\u003c\/p\u003e \u003cp\u003e10.2.3 Other techniques 274\u003c\/p\u003e \u003cp\u003e10.3 Characterization of the global disorder and elastic strain 275\u003c\/p\u003e \u003cp\u003e10.3.1 Raman spectroscopy 275\u003c\/p\u003e \u003cp\u003e10.3.2 Ion beam analysis 277\u003c\/p\u003e \u003cp\u003e10.3.3 X-ray diffraction 280\u003c\/p\u003e \u003cp\u003e10.4 Imaging of extended defects and cavities 282\u003c\/p\u003e \u003cp\u003e10.5 Elemental analysis 284\u003c\/p\u003e \u003cp\u003e10.6 In situ microstructural characterization of materials subjected to irradiation 286\u003c\/p\u003e \u003cp\u003e10.7 Conclusion and perspectives 288\u003c\/p\u003e \u003cp\u003e10.8 References 289\u003c\/p\u003e \u003cp\u003eList of Authors 293\u003c\/p\u003e \u003cp\u003eIndex 295 \u003c\/p\u003e\u003c\/font\u003e\u003c\/p\u003e\r\n\r\n\u003cp\u003e\u003cfont size=\"3\"\u003eSubject Areas: Archaeology [\u003ca title=\"See our other books on Archaeology\" href=\"https:\/\/freshlyprintedbooks.co.uk\/search?q=%22Archaeology%20%5BHD%5D%22\"\u003eHD\u003c\/a\u003e]\u003c\/font\u003e\u003c\/p\u003e\r\n\r\n\r\n\u003c\/font\u003e","brand":"Wiley-ISTE","offers":[{"title":"Brand New","offer_id":52446823973144,"sku":"9781789451481","price":111.99,"currency_code":"GBP","in_stock":true}],"thumbnail_url":"\/\/cdn.shopify.com\/s\/files\/1\/0730\/2037\/5320\/files\/9781789451481.jpg?v=1785114837","url":"https:\/\/freshlyprintedbooks.co.uk\/products\/nuclear-materials-under-irradiation-hardback-9781789451481","provider":"Freshly Printed Books","version":"1.0","type":"link"}