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Handbook of Nuclear Engineering

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Cover of 'Handbook of Nuclear Engineering'

Table of Contents

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    Book Overview
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    Chapter 1 Neutron Cross Section Measurements
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    Chapter 2 Evaluated Nuclear Data
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    Chapter 3 Neutron Slowing Down and Thermalization
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    Chapter 4 Nuclear Data Preparation
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    Chapter 5 General Principles of Neutron Transport
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    Chapter 6 Nuclear Materials and Irradiation Effects
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    Chapter 7 Mathematics for Nuclear Engineering
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    Chapter 8 Multigroup Neutron Transport and Diffusion Computations
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    Chapter 9 Lattice Physics Computations
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    Chapter 10 Core Isotopic Depletion and Fuel Management
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    Chapter 11 Radiation Shielding and Radiological Protection
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    Chapter 12 High Performance Computing in Nuclear Engineering
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    Chapter 13 Analysis of Reactor Fuel Rod Behavior
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    Chapter 14 Noise Techniques in Nuclear Systems
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    Chapter 15 Deterministic and Probabilistic Safety Analysis
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    Chapter 16 Multiphase Flows: Compressible Multi-Hydrodynamics
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    Chapter 17 Sensitivity and Uncertainty Analysis, Data Assimilation, and Predictive Best-Estimate Model Calibration
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    Chapter 18 Reactor Physics Experiments on Zero Power Reactors
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    Chapter 19 Pressurized LWRs and HWRs in the Republic of Korea
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    Chapter 20 VVER-Type Reactors of Russian Design
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    Chapter 21 Sodium Fast Reactor Design: Fuels, Neutronics, Thermal-Hydraulics, Structural Mechanics and Safety
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    Chapter 22 Gas-Cooled Reactors
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    Chapter 23 Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design
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    Chapter 24 GEM*STAR: The Alternative Reactor Technology Comprising Graphite, Molten Salt, and Accelerators
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    Chapter 25 Front End of the Fuel Cycle
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    Chapter 26 Transuranium Elements in the Nuclear Fuel Cycle
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    Chapter 27 Decommissioning of Nuclear Plants
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    Chapter 28 The Scientific Basis of Nuclear Waste Management
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    Chapter 29 Proliferation Resistance and Safeguards
Attention for Chapter 23: Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design
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Chapter title
Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design
Chapter number 23
Book title
Handbook of Nuclear Engineering
Published by
Springer, Boston, MA, January 2010
DOI 10.1007/978-0-387-98149-9_23
Book ISBNs
978-0-387-98130-7, 978-0-387-98149-9
Authors

Luciano Cinotti, Craig F. Smith, Carlo Artioli, Giacomo Grasso, Giovanni Corsini, Cinotti, Luciano, Smith, Craig F., Artioli, Carlo, Grasso, Giacomo, Corsini, Giovanni

Mendeley readers

Mendeley readers

The data shown below were compiled from readership statistics for 42 Mendeley readers of this research output. Click here to see the associated Mendeley record.

Geographical breakdown

Country Count As %
United Kingdom 2 5%
United States 1 2%
Unknown 39 93%

Demographic breakdown

Readers by professional status Count As %
Researcher 9 21%
Student > Ph. D. Student 7 17%
Student > Master 6 14%
Other 4 10%
Student > Bachelor 2 5%
Other 4 10%
Unknown 10 24%
Readers by discipline Count As %
Engineering 14 33%
Physics and Astronomy 6 14%
Energy 4 10%
Materials Science 2 5%
Chemistry 2 5%
Other 0 0%
Unknown 14 33%