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Neutron transport :: theory, modeling, and computations / |
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ISBN/ISSN:
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9783031269349 价格： CNY498.65 |
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ISBN/ISSN:
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9783031269318 |
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ISBN/ISSN:
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3031269314 |
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科图分类法:
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TL329 |
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著者:
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Kuridan, Ramadan M. |
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题名:
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Neutron transport [theory, modeling, and computations ] |
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出版发行:
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Cham : Springer, 2023. |
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载体形态:
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xii, 282 p. : ill. (some color) ; 24 cm. |
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内容提要:
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This textbook provides a thorough explanation of the physical concepts and presents the general theory of different forms through approximations of the neutron transport processes in nuclear reactors and emphasize the numerical computing methods that lead to the prediction of neutron behavior. Detailed derivations and thorough discussions are the prominent features of this book unlike the brevity and conciseness which are the characteristic of most available textbooks on the subject where students find them difficult to follow. This conclusion has been reached from the experience gained through decades of teaching. The topics covered in this book are suitable for senior undergraduate and graduate students in the fields of nuclear engineering and physics. Other engineering and science students may find the construction and methodology of tackling problems as presented in this book appealing from which they can benefit in solving other problems numerically. The book provides access to a one dimensional, two energy group neutron diffusion program including a user manual, examples, and test problems for student practice. An option of a Matlab user interface is also available. |
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主题词:
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Neutron transport theory. |
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主题词:
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Nuclear reactors. |
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HEA| |02538cam a2200289 450 001| |022025003667 008| |231005s2023 sz a b 000 0 eng d 020| |▼a9783031269349▼q(paperback) :- | |▼cCNY498.65 020| |▼a9783031269318▼q(hardback) 020| |▼a3031269314▼q(hardback) 020| |▼z9783031269325▼q(electronic bk.) 020| |▼z3031269322▼q(electronic bk.) 040| |▼aGW5XE▼cGW5XE▼dEBLCP▼dYDX▼dOC- | |LCO▼dOCLCF▼dOCLCQ▼dOCLCO▼dUKAHL▼dOCLCL 050| 4|▼aQC793.5.N4628▼bK87 2023 082|04|▼a539.7▼223/eng/20231005 090| |▼aTL329▼b207956 100|1 |▼aKuridan, Ramadan M.▼eauthor. 245|10|▼aNeutron transport :▼btheory,- | | modeling, and computations /▼- | |cRamadan M. Kuridan. 260| |▼aCham :▼bSpringer,▼c2023. 300| |▼axii, 282 p. :▼bill. (some co- | |lor) ;▼c24 cm. 490|1 |▼aGraduate texts in physics,▼x1868-4521 504| |▼aIncludes bibliographical references. 505|0 |▼aNeutron Transport : The Neut- | |ron Transport Equation －－ Neut- | |ron Diffusion - The Finite Dif- | |ference Solution of The Neutro- | |n Diffusion Equation －－ Spheri- | |cal Harmonics : The PN Method - | |－－ The Adjoint Transport Equat- | |ion : The Equation of Neutron - | |Importance －－ Perturbation The- | |ory －－ The Method of Discrete - | |Ordinates The SN Method. 520| |▼aThis textbook provides a tho- | |rough explanation of the physi- | |cal concepts and presents the - | |general theory of different fo- | |rms through approximations of - | |the neutron transport processe- | |s in nuclear reactors and emph- | |asize the numerical computing - | |methods that lead to the predi- | |ction of neutron behavior. Det- | |ailed derivations and thorough- | | discussions are the prominent- | | features of this book unlike - | |the brevity and conciseness wh- | |ich are the characteristic of - | |most available textbooks on th- | |e subject where students find - | |them difficult to follow. This- | | conclusion has been reached f- | |rom the experience gained thro- | |ugh decades of teaching. The t- | |opics covered in this book are- | | suitable for senior undergrad- | |uate and graduate students in - | |the fields of nuclear engineer- | |ing and physics. Other enginee- | |ring and science students may - | |find the construction and meth- | |odology of tackling problems a- | |s presented in this book appea- | |ling from which they can benef- | |it in solving other problems n- | |umerically. The book provides - | |access to a one dimensional, t- | |wo energy group neutron diffus- | |ion program including a user m- | |anual, examples, and test prob- | |lems for student practice. An - | |option of a Matlab user interf- | |ace is also available. 650| 0|▼aNeutron transport theory. 650| 0|▼aNuclear reactors. 830| 0|▼aGraduate texts in physics.