000			03475cam a22004697i 4500
001			11268
003			MEMOS
005			20240731094755.0
008			190426s2019 enka b 001 0 eng d
010			_a 2019941583
020			_a9780081023372 _qpaperback
020			_a0081023375 _qpaperback
035			_a(OCoLC)on1004366649
040			_aMEMOS _beng _cYDX _erda _dMEMOS _dYDXIT _dBDX _dOCLCF _dV5E _dLTSCA _dOCL _dDLC
042			_alccopycat
050	0	0	_aTK9202 _b.A283 2019
080			_a621.039.58:532 _bA38
082	0	4	_a621.48/3 _223 _bA244
245	0	0	_aAdvances of computational fluid dynamics in nuclear reactor design and safety assessment / _cedited by Jyeshtharaj B. Joshi, Arun K. Nayak.
260			_a Duxford, United Kingdom : _bWoodhead Publishing, an imprint of Elsevier, _c[2019]
264		1	_a _a _b _c
300			_axiii, 869 pages : _billustrations (chiefly color) ; _c23 cm
336			_atext _btxt _2rdacontent
337			_aunmediated _bn _2rdamedia
338			_avolume _bnc _2rdacarrier
490	1		_aWoodhead Publishing series in energy
504			_aIncludes bibliographical references and index.
505	0		_aIntroduction -- Computational fluid dynamics -- CFD model development for two-phase flows -- Evaluation of safety of light-water-cooled reactors using CFD -- Design of passive safety systems for advanced reactors using CFD -- Modelling of core melt scenarios in nuclear reactors -- Application of CFD for assessment of containment safety -- Modeling of fire with CFD for nuclear power plants (NPPs) -- Applications of computational fluid dynamics in design of sodium-cooled fast reactors -- CFD and systems thermal-hydraulic analysis in the design and safety assessment of high-temperature reactors -- Heat transfer and computational fluid dynamics for molten salt reactor technologies -- Conclusions and future recommendations.
520			_aAdvances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors. Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants.-- _cSource other than the Library of Congress.
650		0	_aNuclear reactors _xDesign and construction.
650		0	_aNuclear reactors _xSafety measures.
650		0	_aComputational fluid dynamics.
650		7	_aNuclear reactors _xSafety measures. _2fast _0(OCoLC)fst01040845
650		7	_aComputational fluid dynamics. _2fast _0(OCoLC)fst01745072
650		7	_aNuclear reactors _xDesign and construction. _2fast _0(OCoLC)fst01040788
700	1		_aJoshi, Jyeshtharaj B., _eeditor.
700	1		_aNayak, Arun K., _eeditor.
830		0	_aWoodhead Publishing in energy.
906			_a44806 _b
942			_2ddc _cBK _n0
999			_c13692 _d13692