S. Chakraverty, Sukanta Nayak
Neutron Diffusion
Concepts and Uncertainty Analysis for Engineers and Scientists
S. Chakraverty, Sukanta Nayak
Neutron Diffusion
Concepts and Uncertainty Analysis for Engineers and Scientists
- Broschiertes Buch
- Merkliste
- Auf die Merkliste
- Bewerten Bewerten
- Teilen
- Produkt teilen
- Produkterinnerung
- Produkterinnerung
This book is designed for a systematic understanding of nuclear diffusion theory along with fuzzy/interval/stochastic uncertainty.
Andere Kunden interessierten sich auch für
- Ferdinand F CapMathematical Methods in Physics and Engineering with Mathematica94,99 €
- David Y GaoIntroduction to Asymptotic Methods94,99 €
- T S L RadhikaApproximate Analytical Methods for Solving Ordinary Differential Equations94,99 €
- A a MartynyukUncertain Dynamical Systems94,99 €
- Drumi D BainovDifferential Equations with Maxima94,99 €
- John A BurnsIntroduction to the Calculus of Variations and Control with Modern Applications93,99 €
- Luis Manuel Braga De Costa CamposGeneralized Calculus with Applications to Matter and Forces87,99 €
-
-
-
This book is designed for a systematic understanding of nuclear diffusion theory along with fuzzy/interval/stochastic uncertainty.
Hinweis: Dieser Artikel kann nur an eine deutsche Lieferadresse ausgeliefert werden.
Hinweis: Dieser Artikel kann nur an eine deutsche Lieferadresse ausgeliefert werden.
Produktdetails
- Produktdetails
- Verlag: Taylor & Francis Ltd (Sales)
- Seitenzahl: 196
- Erscheinungstermin: 10. Dezember 2019
- Englisch
- Abmessung: 254mm x 178mm x 11mm
- Gewicht: 349g
- ISBN-13: 9780367889807
- ISBN-10: 0367889803
- Artikelnr.: 58483210
- Herstellerkennzeichnung
- Libri GmbH
- Europaallee 1
- 36244 Bad Hersfeld
- 06621 890
- Verlag: Taylor & Francis Ltd (Sales)
- Seitenzahl: 196
- Erscheinungstermin: 10. Dezember 2019
- Englisch
- Abmessung: 254mm x 178mm x 11mm
- Gewicht: 349g
- ISBN-13: 9780367889807
- ISBN-10: 0367889803
- Artikelnr.: 58483210
- Herstellerkennzeichnung
- Libri GmbH
- Europaallee 1
- 36244 Bad Hersfeld
- 06621 890
Dr. S. Chakraverty has over 25 years of experience as a researcher and teacher. Currently he is working at the National Institute of Technology, Rourkela, Odisha as a full Professor and Head of the Department of Mathematics. Prior to this he was with CSIR Central Building Research Institute, Roorkee, India. After graduating from St. Columba's College (Ranchi University), he obtained his M. Sc in Mathematics and M. Phil in Computer Applications from the University of Roorkee (now the Indian Institute of Technology Roorkee), earning First Position in the University honors. Dr. Chakraverty received his Ph. D. from IIT Roorkee in 1992. Thereafter he did his post-doctoral research at Institute of Sound and Vibration Research (ISVR), University of Southampton, U.K. and at the Faculty of Engineering and Computer Science, Concordia University, Canada. He was also a visiting professor at Concordia and McGill Universities, Canada, during 1997-1999 and visiting professor of University of Johannesburg, South Africa during 2011-2014. Sukanta Nayak received his B.Sc. (Mathematics) from Government Autonomous College, Rourkela in 2008 and M.Sc. (Mathematics) from National Institute of Technology, Rourkela in 2010. He has done his Ph. D. (Mathematics) from National Institute of Technology, Rourkela in 2016. He is the awardee of P. G. level scholarship, Government of Odisha in 2008 and qualified GATE, Government of India, in 2012. Currently he is doing his post-doctoral research at the University of Johannesburg, South Africa. He has published 9 research papers in international peer-reviewed journals, and 2 book chapters.
Basic Reactor Principles
Atomic Structure
Binding energy
Nuclear fusion
Nuclear fission
Radioactivity
Principles, Production, and interaction of neutrons with matter
Production of neutrons
Neutron reactions and radiation
Inelastic and elastic scattering of neutrons
Maxwell-Boltzmann distribution
Neutron diffusion theory
Cross section of neutron reactions
Rates of neutron reactions
Fission neutrons
Prompt neutrons
Delayed neutrons
Neutron transport and diffusion equation
Fundamentals of Uncertainty
Probabilistic uncertainty
Non-probabilistic uncertainty
Interval uncertainty
Fuzzy uncertainty
Uncertain Neutron diffusion
Uncertain factors involved in neutron diffusion theory
Modeling of uncertain neutron diffusion equations
One group model
Analytical methods
Numerical methods
Finite difference method
Finite element method
Conclusion
Uncertain One Group Model
Interval arithmetic and Fuzzy Finite Element Method (FFEM)
Formulation of the uncertain stiffness matrices and force vectors
Bare square homogeneous reactor
Multi group model
Uncertain factors involved in multi group neutron diffusion theory
Formulation of uncertain multi group neutron diffusion equations
Uncertain Multi Group Model
Fuzzy finite element for coupled differential equations
Fuzzy multi group neutron diffusion equation
Case study
Results and discussion
Conclusion
Point Kinetic Diffusion
Theory of point kinetic neutron diffusion equation
Case study
Conclusion
Stochastic Point Kinetic Diffusion
Stochastic point kinetic model
Eu
Atomic Structure
Binding energy
Nuclear fusion
Nuclear fission
Radioactivity
Principles, Production, and interaction of neutrons with matter
Production of neutrons
Neutron reactions and radiation
Inelastic and elastic scattering of neutrons
Maxwell-Boltzmann distribution
Neutron diffusion theory
Cross section of neutron reactions
Rates of neutron reactions
Fission neutrons
Prompt neutrons
Delayed neutrons
Neutron transport and diffusion equation
Fundamentals of Uncertainty
Probabilistic uncertainty
Non-probabilistic uncertainty
Interval uncertainty
Fuzzy uncertainty
Uncertain Neutron diffusion
Uncertain factors involved in neutron diffusion theory
Modeling of uncertain neutron diffusion equations
One group model
Analytical methods
Numerical methods
Finite difference method
Finite element method
Conclusion
Uncertain One Group Model
Interval arithmetic and Fuzzy Finite Element Method (FFEM)
Formulation of the uncertain stiffness matrices and force vectors
Bare square homogeneous reactor
Multi group model
Uncertain factors involved in multi group neutron diffusion theory
Formulation of uncertain multi group neutron diffusion equations
Uncertain Multi Group Model
Fuzzy finite element for coupled differential equations
Fuzzy multi group neutron diffusion equation
Case study
Results and discussion
Conclusion
Point Kinetic Diffusion
Theory of point kinetic neutron diffusion equation
Case study
Conclusion
Stochastic Point Kinetic Diffusion
Stochastic point kinetic model
Eu
Basic Reactor Principles
Atomic Structure
Binding energy
Nuclear fusion
Nuclear fission
Radioactivity
Principles, Production, and interaction of neutrons with matter
Production of neutrons
Neutron reactions and radiation
Inelastic and elastic scattering of neutrons
Maxwell-Boltzmann distribution
Neutron diffusion theory
Cross section of neutron reactions
Rates of neutron reactions
Fission neutrons
Prompt neutrons
Delayed neutrons
Neutron transport and diffusion equation
Fundamentals of Uncertainty
Probabilistic uncertainty
Non-probabilistic uncertainty
Interval uncertainty
Fuzzy uncertainty
Uncertain Neutron diffusion
Uncertain factors involved in neutron diffusion theory
Modeling of uncertain neutron diffusion equations
One group model
Analytical methods
Numerical methods
Finite difference method
Finite element method
Conclusion
Uncertain One Group Model
Interval arithmetic and Fuzzy Finite Element Method (FFEM)
Formulation of the uncertain stiffness matrices and force vectors
Bare square homogeneous reactor
Multi group model
Uncertain factors involved in multi group neutron diffusion theory
Formulation of uncertain multi group neutron diffusion equations
Uncertain Multi Group Model
Fuzzy finite element for coupled differential equations
Fuzzy multi group neutron diffusion equation
Case study
Results and discussion
Conclusion
Point Kinetic Diffusion
Theory of point kinetic neutron diffusion equation
Case study
Conclusion
Stochastic Point Kinetic Diffusion
Stochastic point kinetic model
Eu
Atomic Structure
Binding energy
Nuclear fusion
Nuclear fission
Radioactivity
Principles, Production, and interaction of neutrons with matter
Production of neutrons
Neutron reactions and radiation
Inelastic and elastic scattering of neutrons
Maxwell-Boltzmann distribution
Neutron diffusion theory
Cross section of neutron reactions
Rates of neutron reactions
Fission neutrons
Prompt neutrons
Delayed neutrons
Neutron transport and diffusion equation
Fundamentals of Uncertainty
Probabilistic uncertainty
Non-probabilistic uncertainty
Interval uncertainty
Fuzzy uncertainty
Uncertain Neutron diffusion
Uncertain factors involved in neutron diffusion theory
Modeling of uncertain neutron diffusion equations
One group model
Analytical methods
Numerical methods
Finite difference method
Finite element method
Conclusion
Uncertain One Group Model
Interval arithmetic and Fuzzy Finite Element Method (FFEM)
Formulation of the uncertain stiffness matrices and force vectors
Bare square homogeneous reactor
Multi group model
Uncertain factors involved in multi group neutron diffusion theory
Formulation of uncertain multi group neutron diffusion equations
Uncertain Multi Group Model
Fuzzy finite element for coupled differential equations
Fuzzy multi group neutron diffusion equation
Case study
Results and discussion
Conclusion
Point Kinetic Diffusion
Theory of point kinetic neutron diffusion equation
Case study
Conclusion
Stochastic Point Kinetic Diffusion
Stochastic point kinetic model
Eu