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008			121128s2013 enka b 001 0 eng d
010			_a 2012954753
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020			_a9780857092397
020			_a0857092391
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042			_alccopycat
050	0	0	_aTK9185 _b.M38 2013
082	0	4	_a621.4833 _223
245	0	0	_aMaterials' ageing and degradation in light water reactors : _bmechanisms and management / _cedited by K.L. Murty.
300			_axxi, 417 pages : _billustrations ; _c24 cm.
490	1		_aWoodhead Publishing in energy, _x2044-9364 ; _v44
504			_aIncludes bibliographical references and index.
505	0		_aMachine generated contents note: pt. I Fundamental ageing issues and degradation mechanisms -- 1. Overview of ageing and degradation issues in light water reactors (LWRs) / K. Ramaswamy -- 1.1. Introduction -- 1.2. Degradation mechanisms and materials ageing issues in nuclear steam supply systems (NSSS) -- 1.3. Radiation effects -- 1.4. Degradation mechanisms of specific nuclear reactor structures -- 1.5. Conclusions -- 1.6. References -- 2. Corrosion in pressurized water reactors (PWRs) / T. Couvant -- 2.1. Introduction -- 2.2. Pressurized water reactors and the main types of corrosion -- 2.3. Major components experiencing corrosion -- 2.4. Conclusion -- 2.5. References -- 3. Creep deformation of materials in light water reactors (LWRs) / I. Charit -- 3.1. Introduction -- 3.2. Standard creep equations -- 3.3. Identifying the mechanisms of creep -- 3.4. Rate controlling mechanisms and activation energy -- 3.5. Transitions in creep mechanisms -- 3.6. Modeling creep life: extrapolation of strain and rupture data -- 3.7. Case studies illustrating the role of other factors -- 3.8. Creep of zirconium alloys used for LWR cladding -- 3.9. References -- pt. II Materials ageing and degradation in particular light water reactor (LWR) components -- 4. Properties of zirconium alloys and their applications in light water reactors (LWRs) / P. Rudling -- 4.1. Introduction -- 4.2. Fuel assembly designs -- 4.3. Effects of irradiation on zirconium alloys -- 4.4. Mechanical properties of zirconium alloys -- 4.5. Corrosion of zirconium alloys -- 4.6. Dimensional stability of zirconium alloys -- 4.7. Future trends and research needs -- 4.8. Sources of further information -- 4.9. Acknowledgements -- 4.10. References -- 5. Performance and inspection of zirconium alloy fuel bundle components in light water reactors (LWRs) / R.B. Adamson -- 5.1. Introduction -- 5.2. Materials performance during normal operational conditions -- 5.3. Materials performance during accidents -- 5.4. Materials performance during interim dry storage -- 5.5. Inspection methods -- 5.6. Future trends and research needs -- 5.7. Sources of further information and advice -- 5.8. Acknowledgements -- 5.9. References -- 6. Ageing of electric cables in light water reactors (LWRs) / H.M. Hashemian -- 6.1. Introduction -- 6.2. Cable degradation issues -- 6.3. Analysis and assessment methods -- 6.4. Residual life modeling -- 6.5. Development and application of cable ageing mitigation routes -- 6.6. Sources of further information -- 6.7. References -- pt. III Materials management strategies for light water reactors (LWRs) -- 7. Materials management strategies for pressurized water reactors (PWRs) / S.S. Hwang -- 7.1. Introduction -- 7.2. Materials management strategies -- 7.3. Management techniques: development and application -- 7.4. Case studies of management strategies -- 7.5. References -- 8. Materials management strategies for VVER reactors / T.J. Katona -- 8.1. Introduction -- 8.2. Description of operating VVER reactors -- 8.3. Ageing of the VVERs -- plant operational experience -- 8.4. Ensuring safety for a long-term operation -- 8.5. Plant programmes credited for long-term operation -- 8.6. Conclusion -- 8.7. References -- 9. Materials-related problems faced by light water reactor (LWR) operators and corresponding research needs / E. Lahoda -- 9.1. Introduction -- 9.2. Fuel and cladding materials -- the first fission barrier -- 9.3. The primary system -- the second fission barrier -- 9.4. The containment structure -- the final fission barrier -- 9.5. Other nuclear reactor systems -- 9.6. References.
650		0	_aNuclear engineering _xMaterials.
650		0	_aLight water reactors _xMaterials _xDeterioration.
650		7	_aLight water reactors. _2fast
650		7	_aLight water reactors _xSafety measures. _2fast
700	1		_aeditor Murty, K. Linga.
830		0	_aWoodhead Publishing in energy ; _vno. 44.
856	4	1	_uhttp://www.woodheadpublishingonline.com/content/uv7600?entityid=https://passport01.leeds.ac.uk/idp/shibboleth _zView this book online, via Woodhead Publishing, both on- and off-campus
856	4	1	_uhttp://0-www.sciencedirect.com.wam.leeds.ac.uk/science/book/9780857092397 _zView this book online, via Woodhead Publishing, both on- and off-campus
856	4	2	_3Publisher description _uhttp://www.loc.gov/catdir/enhancements/fy1506/2012954753-d.html
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