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paperback. Condizione: New. Ship out in 2 business day, And Fast shipping, Free Tracking number will be provided after the shipment.Paperback. Pub Date: 2012 Pages: 339 Language: Offset Paper Publisher: China University of Science and Technology Publishing House of China University of Science and Technology boutique textbook: Nuclear Physics and Technology Introduction at the China University of Science and Technology graduate students through courses in 2005 to 2011 speech on the basis of finishing. Its purpose is under the framework of the Nuclear Energy Science and Engineering. unified. comprehensive description of basic knowledge. the concept of nuclear energy. especially for neutron transport equations. formulas and procedures. to teach as a unified whole. In addition to Chapter 1 Overview of content. the content of Chapter 2 to Chapter 6 taught mainly related to the fission process. Chapter 7. Chapter 8 and Chapter 10. taught mainly involved in the fusion process. Chapter 9 of accelerator-driven sub-critical system process. the contents of Chapter 11 teaches mainly related to the nuclear fuel cycle. Therefore. China University of Science and Technology Excellent Textbooks: Nuclear Physics and Technology Introduction for graduate teaching. can also be used for the senior undergraduate teaching. as well as research and technical staff for informational purposes. Contents: General Preface Preface Chapter 1 nuclear power 1.1 Einstein great anticipate the E = mc21.2 Keziliyong the type of nuclear energy: fission 1.3 fusion fusion energy can solve human energy needs to select 1.4 Project ITER target 1.5 inertial confinement nuclear fusion 1.6 accelerator driven sub-critical nuclear energy system reference the Chapter 2 neutron nuclear reaction 2.1 neutron About 2.2 neutrons with nuclei interaction 2.3 neutron cross section of the nuclear reaction rate of 2.4 nuclear reaction rate. neutron flux density resonance absorption 2.5-section with the changes in the neutron energy 2.6 2.7 Doppler effect 2.8 nuclear fission process 2.1 Neutron Source Technical Reference Chapter 3 2.9 2.1 2.1 0 neutron fission products and fission neutrons moderated a chain reaction neutron transport theory. the burnup equation and diffusion approximation 3.1 the history of the study of the neutron transport equation 3.2 the boundary conditions of the transport equation 3.3 approximate solving 3.4 reactor burnup theory 3.5 two-dimensional transport burnup the program BUDOT About 3.6 fission reactor theoretical basis - 3.7 pairs of group theory of diffusion approximation reflective layer single-group diffusion theory reactor 3.8 4.1 critical the 3.9 grid non-uniform effect homogenization References Chapter 4 critical systems and neutrons in the subcritical system behavior subcritical REACTOR security features 4.2 subcritical reactors. subcritical reactor neutron theory system delayed neutron fraction 4.4 fusion neutron source strength perturbed system 4.3 4.5 4.6 fusion-driven subcritical reactivity feedback mechanism 4.7 Chapter 5 of the nuclear fission Operation Management and fission product poisoning (iodine pit) References fission reactors direction of China's nuclear power development in the 5.1 fission reactor development process of the main problems facing 5.2 fission reactors now 5.3 5.4 fission reactor design process 5.5 pressurized water reactor (PWR sample 5.6 Advanced Light Water Reactor 5.7 HTGR the HTGR example with reference to fast reactor concept of literature in Chapter 6 of the fast reactor works and the status of 6.1 6.2 fast reactor safety consider 6.3 the advantages and difficulties of fast reactor 6.4) crack substation fast reactor the economy needs to be verified 6.5 fast reactor structure. intermediate circuit 6.6 fast reactor Outlook 6.7 fast reactor status quo 6.8 China Experimental Fast Reactor Development References Chapter 7 fusion reactor 7.1 meaning 7.2 can take advantage of the fusion nuclear research nuclear fusion reaction 7.3 controlled the basic.