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Introduction to nuclear engineering (Record no. 19280)

MARC details
000 -LEADER
fixed length control field 03577nam a22001937a 4500
005 - DATE AND TIME OF LATEST TRANSACTION
control field 20200604211508.0
008 - FIXED-LENGTH DATA ELEMENTS--GENERAL INFORMATION
fixed length control field 191202b ||||| |||| 00| 0 eng d
020 ## - INTERNATIONAL STANDARD BOOK NUMBER
International Standard Book Number 9789332536708 (pbk)
040 ## - CATALOGING SOURCE
Transcribing agency PK-IsLIS
082 ## - DEWEY DECIMAL CLASSIFICATION NUMBER
Classification number 621.48
Item number L163
100 ## - MAIN ENTRY--PERSONAL NAME
Personal name Lamarsh, John R.
245 ## - TITLE STATEMENT
Title Introduction to nuclear engineering
Statement of responsibility, etc / John R. Lamarsh, Anthony J. Baratta
250 ## - EDITION STATEMENT
Edition statement 3rd ed.
260 ## - PUBLICATION, DISTRIBUTION, ETC. (IMPRINT)
Place of publication, distribution, etc Uttar Pradesh :
Name of publisher, distributor, etc Pearson Education,
Date of publication, distribution, etc 2014
300 ## - PHYSICAL DESCRIPTION
Extent 740 p.
650 ## - SUBJECT ADDED ENTRY--TOPICAL TERM
Topical term or geographic name as entry element Nuclear engineering
942 ## - ADDED ENTRY ELEMENTS (KOHA)
Koha item type Books
505 0# - FORMATTED CONTENTS NOTE
Formatted contents note (Most chapters end with References and Problems). 1. Nuclear Engineering. 2. Atomic and Nuclear Physics. Fundamental Particles. Atomic and Nuclear Structure. Atomic and Molecular Weight. Atomic and Nuclear Radii. Mass and Energy. Particle Wavelengths. Excited States and Radiation. Nuclear Stability and Radioactive Decay. Radioactivity Calculations. Nuclear Reactions. Binding Energy. Nuclear Models. Gases, Liquids, and Solids. Atom Density.3. Interaction of Radiation with Matter. Neutron Interactions. Cross-Sections. Neutron Attenuation. Neutron Flux. Neutron Cross-Section Data. Energy Loss in Scattering Collisions. Fission. y-Ray Interactions with Matter. Charged Particles. 4. Nuclear Reactors and Nuclear Power. The Fission Chain Reaction. Nuclear Reactor Fuels. Non-Nuclear Components of Nuclear Power Plants. Components of Nuclear Reactors. Power Reactors and Nuclear Steam Supply Systems. Nuclear Cycles. Isotope Separation. Fuel Reprocessing. Radioactive Waste Disposal.5. Neutron Diffusion and Moderation. Neutron Flux. Fick's Law. The Equation of Continuity. The Diffusion Equation. Boundary Conditions. Solutions of the Diffusion Equation. The Diffusion Length. The Group-Diffusion Method. Thermal Neutron Diffusion. Two-Group Calculation of Neutron Moderation.6. Nuclear Reactor Theory. One-Group Reactor Equation. The Slab Reactor. Other Reactor Shapes. The One-Group Critical Equation. Thermal Reactors. Reflected Reactors. Multigroup Calculations. Heterogeneous Reactors.7. The Time-Dependent Reactor. Classification of Time Problems. Reactor Kinetics. Control Rods and Chemical Shim. Temperature Effects on Reactivity. Fission Product Poisoning. Core Properties during Lifetime.8. Heat Removal from Nuclear Reactors. General Thermodynamic Considerations. Heat Generation in Reactors. Heat Flow by Conduction. Heat Transfer to Coolants. Boiling Heat Transfer. Thermal Design of a Reactor.9. Radiation Protection. History of Radiation Effects. Radiation Units. Some Elementary Biology. The Biological Effects of Radiation. Quantitative Effects of Radiation on the Human Species. Calculations of Radiation Effects. Natural and Man-Made Radiation Sources. Standards of Radiation Protection. Computations of Exposure and Dose. Standards for Intake of Radionuclides. Exposure from y-Ray Sources. Glossary.10. Radiation Shielding. Gamma-Ray Shielding: Buildup Factors. Infinite Planar and Disc Sources. The Line Source. Internal Sources. Multilayered Shields. Nuclear Reactor Shielding: Principles of Reactor Shielding. Removal Cross-Sections. The Reactor Shield Design: Removal-Attenuation Calculatons. The Removal-Diffusion Method. Exact Methods. Shielding y-Rays. Coolant Activation. Ducts in Shields.11. Reactor Licensing, Safety, and the Environment. Governmental Authority and Responsibility. Reactor Licensing. Principles of Nuclear Power Plant Safety. Dispersion of Effluents from Nuclear Facilities. Radiation Doses from Nuclear Plants. Reactor Siting. Reactor Accidents. Accident Risk Analysis. Environmental Radiation Doses
Holdings
Withdrawn status Damaged status Not for loan Home library Current library Date acquired Source of acquisition Full call number Barcode Date last seen Copy number Price effective from Koha item type
      UE-Central Library UE-Central Library 02.12.2019 U.E. 621.48 L163 T12800 02.12.2019 c. 2 02.12.2019 Books
      UE-Central Library UE-Central Library 02.12.2019 U.E. 621.48 L163 T12799 02.12.2019 c. 1 02.12.2019 Books
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