Author: Paul Michael KellerPublisher:
ISBN:
Category :
Languages : en
Pages : 354
Book Description
A Collision Probability Method for One-dimensional Space-time Nuclear Reactor Kinetics
Author: Paul Michael KellerNuclear Science Abstracts
Author: Nuclear Science Abstracts
Author: Scientific and Technical Aerospace Reports
Author: Energy Research Abstracts
Author: Neutral Particle Integral Transport in Inertial Confinement of Fusion Systems Using Time Dependent Integral Transport Methods
Author: K. R. OlsonNuclear News
Author: Nuclear Engineering
Author: Zafar Ullah KoreshiPublisher: Academic Press
ISBN: 0323908314
Category : Science
Languages : en
Pages : 549
Book Description
Nuclear Engineering Mathematical Modeling and Simulation presents the mathematical modeling of neutron diffusion and transport. Aimed at students and early career engineers, this highly practical and visual resource guides the reader through computer simulations using the Monte Carlo Method which can be applied to a variety of applications, including power generation, criticality assemblies, nuclear detection systems, and nuclear medicine to name a few. The book covers optimization in both the traditional deterministic framework of variational methods and the stochastic framework of Monte Carlo methods. Specific sections cover the fundamentals of nuclear physics, computer codes used for neutron and photon radiation transport simulations, applications of analyses and simulations, optimization techniques for both fixed-source and multiplying systems, and various simulations in the medical area where radioisotopes are used in cancer treatment. Provides a highly visual and practical reference that includes mathematical modeling, formulations, models and methods throughout Includes all current major computer codes, such as ANISN, MCNP and MATLAB for user coding and analysis Guides the reader through simulations for the design optimization of both present-day and future nuclear systems
INIS Atomindex
Author: The Physics of Nuclear Reactors
Author: Serge MarguetPublisher: Springer
ISBN: 3319595601
Category : Science
Languages : en
Pages : 1462
Book Description
This comprehensive volume offers readers a progressive and highly detailed introduction to the complex behavior of neutrons in general, and in the context of nuclear power generation. A compendium and handbook for nuclear engineers, a source of teaching material for academic lecturers as well as a graduate text for advanced students and other non-experts wishing to enter this field, it is based on the author’s teaching and research experience and his recognized expertise in nuclear safety. After recapping a number of points in nuclear physics, placing the theoretical notions in their historical context, the book successively reveals the latest quantitative theories concerning: • The slowing-down of neutrons in matter • The charged particles and electromagnetic rays • The calculation scheme, especially the simplification hypothesis • The concept of criticality based on chain reactions • The theory of homogeneous and heterogeneous reactors • The problem of self-shielding • The theory of the nuclear reflector, a subject largely ignored in literature • The computational methods in transport and diffusion theories Complemented by more than 400 bibliographical references, some of which are commented and annotated, and augmented by an appendix on the history of reactor physics at EDF (Electricité De France), this book is the most comprehensive and up-to-date introduction to and reference resource in neutronics and reactor theory.