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Introduction To Nuclear Engineering. Second Edition. [With Illustrations.].

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  • Book Title: Introduction to Nuclear Engineering. Second Edition. [With Illustrations.].
  • ISBN 13:
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  • Author: Raymond Le Roy MURRAY
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  • Format & Number of pages: 384 pages, book
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Lamarsh J

Lamarsh J.R. Introduction to nuclear engineering

2nd Edition, Addison-Wesley Publ. Co, Massachusetts, 1983, 702 pp. - ISBN 0-201-14200-7
This book is derived from classroom notes which were prepared for three courses offered by the Department of Nuclear Engineering at New York University and the Polytechnic Institute of New York. These are a one-year introductory course in nuclear engineering (Chapters 1-8), a one-term course in radiation protection (Chapters 9 and 10), and a one-term course in reactor licensing, safety, and the environment (Chapter 11). These courses are offered to juniors and seniors in the Department's undergraduate program and to beginning graduate students who have not had previous training in nuclear engineering.
Contents:
The Scope of Nuclear Engineering.
Atomic and Nuclear Physics.
Interaction of Radiation with Matter.
Nuclear Reactors and Nuclear Power.
Neutron Diffusion and Moderation
Nuclear Reactor Theory.
The Time-Dependent Reactor (Reactor Kinetics).
Heat Removal from Nuclear Reactors.
Radiation Protection.
Radiation Shielding.
Reactor Licensing, Safety, and the Environment.
Appendixes.
Index.

CRC Press, 2009, 790 pp. -ISBN - 978-1-4200-5390-6.
The purpose of this Handbook is to provide an introduction to nuclear power reactors, the nuclear fuel cycle, and associated analysis tools, to a broad audience including engineers, engineering and science students, their teachers and mentors, science and technology journal.

Springer, 2010. 3600 p. ISBN-10:0387981306

The Handbook of Nuclear Engineering is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all academic levels, this five volume set provides the latest findings in nuc.

Springer, 2005, Pages: 442

This book is an introduction to nuclear principles with special emphasis on engineering applications. Topics such as neutron physics, nuclear structure and radiation interactions are illustrated through numerous examples that include detailed solutions and links to theory. The reader will fin.

Kansas State University Manhattan, Marcel Dekker, New York, Basel, 2002, 506 pp. - ISBN 0-8247-0834-2.
Nuclear engineering and the technology developed by this discipline began and reached an amazing level of maturity within the past 60 years. Although nuclear and atomic radiation had been used during the first half of the t.

Kansas State University Manhattan, Marcel Dekker, New York, Basel, 2002, 506 pp. - ISBN 0-8247-0834-2.
Nuclear engineering and the technology developed by this discipline began and reached an amazing level of maturity within the past 60 years. Although nuclear and atomic radiation had been used during the first half of the t.

Second Edition, McGraw-Hill, New York, San Francisco, Hamburg, 1981, 1078 pp. - ISBN 0-07-004531-3.
The development of nuclear fission chain reactors for the conversion of mass to energy and the transmutation of elements has brought into industrial prominence chemical substances and chemical engineering processes that a few.

Elsevier, 2006, 447 pp. - ISBN 13: 978-0-7506-6723-4.
Contents:
Preface.
Introduction.
Inventory and localization of radioactive products in the plant.
Safety systems and their functions.
The classification of accidents and a discussion of some examples.
Severe accidents.
The dispersion of radioac.

Woodhead Publishing Limited, 2011, 492 pages

Advanced separations technology is key to closing the nuclear fuel cycle and relieving future generations from the burden of radioactive waste produced by the nuclear power industry. Nuclear fuel reprocessing techniques not only allow for recycling of useful fuel components.

Facts on File, 2011, 164 pages

The discovery and application of nuclear power is one of the most profound scientific accomplishments of the 20th century, beginning with tentative explorations of the structure of matter, expanding into a rapid succession of unexpected discoveries, and finally settling into a seamless t.

Second edition, Springer Science+Business Media, New York, 2009, 557 pp. - ISBN 978-0-387-85607-0.
This book offers background and a basis for technology development in inherently safe reactors, medical imaging and integrated cancer therapies, food technology, radiation shielding, and nuclear space applications. It is intend.

Source:

www.exlit.ru

Articles

Wong S

Wong S.S.M. Introductory Nuclear Physics

2nd edition, Wiley-VCH Verlag, 2004, 460 pages, ISBN: 0471239739

A comprehensive, unified treatment of present-day nuclear physics-the fresh edition of a classic text/reference.

What sets Introductory Nuclear Physics apart from other books on the subject is its presentation of nuclear physics as an integral part of modern physics. Placing the discipline within a broad historical and scientific context, it makes important connections to other fields such as elementary particle physics and astrophysics.

Now fully revised and updated, this Second Edition explores the changing directions in nuclear physics, emphasizing new developments and current research-from superdeformation to quark-gluon plasma. Author Samuel S.M. Wong preserves those areas that established the First Edition as a standard text in university physics departments, focusing on what is exciting about the discipline and providing a concise, thorough, and accessible treatment of the fundamental aspects of nuclear properties.

In this new edition, Professor Wong:
Includes a chapter on heavy-ion reactions-from high-spin states to quark-gluon plasma
Adds a new chapter on nuclear astrophysics
Relates observed nuclear properties to the underlying nuclear interaction and the symmetry principles governing subatomic particles
Regroups material and appendices to make the text easier to use
Lists Internet links to essential databases and research projects
Features end-of-chapter exercises using real-world data.

Introductory Nuclear Physics, Second Edition is an ideal text for courses in nuclear physics at the senior undergraduate or first-year graduate level. It is also an important resource for scientists and engineers working with nuclei, for astrophysicists and particle physicists, and for anyone wishing to learn more about trends in the field.

Introduction
Nucleon Structure
Nuclear Force and Two-Nucleon Systems
Bulk Properties of Nuclei
Electromagnetic and Weak lnteraction
Nuclear Collective Motion
Microscopic Models of Nuclear Structure
Nuclear Reactions
Nuclei under Extreme Conditions
Nuclear Astrophysics
Nuclear Physics: Present and Future

Source:

www.twirpx.com

Lamarsh - Baratta, Introduction to Nuclear Engineering, 3rd Edition

Introduction to Nuclear Engineering, 3rd Edition Description

The text is designed for junior and senior level Nuclear Engineering students.

The third edition of this highly respected text offers the most current and complete introduction to nuclear engineering available. Introduction to Nuclear Engineering has been thoroughly updated with new information on French, Russian, and Japanese nuclear reactors. All units have been revised to reflect current standards. In addition to the numerous end-of-chapter problems, computer exercises have been added.

Previous Edition(s)
Introduction to Nuclear Engineering, 2nd Edition
  • ©1983
  •  | Pearson
  •  | Cloth
  •  | ISBN-13: 9780201142006
Courses

This title is appropriate for the following courses. Select a course to see additional titles

Features
  • NEW - Discussions of new reactor types including the AP600, ABWR, and SBWR as well as an extensive section on non-US design reactors.

    Provides students with the latest in the technology of the industry. Ex.___

  • NEW - The authors have added a discussion on the nuclear Navy and its impact on the development of nuclear energy.
    • Enables a clearer understanding of the importance and use of nuclear power. Ex.___

  • NEW - Basic nuclear theory chapters include additional discussions on binding energy and such topics as the semi-empirical mass formula and elementary quantum mechanics.
    • Increases understanding of the origin of nuclear energy. Ex.___

  • NEW - Changes in reactor theory sections include a more complete discussion of solutions to the diffusion equation and a more general derivation of the point kinetics equation.
    • Enables students to comprehend the theory. Ex.___

  • NEW - Chapter on radiation effects updated to include the latest standards— Both SI and conventional units are discussed and used in examples and problems in this chapter.
    • Prepares students for international interactions. Ex.___

  • NEW - Topics in reactor safety now include a complete discussion of the Chernobyl accident and an updated section on TMI and the use of computer codes in safety analysis.
    • Helps readers to appreciate the inherent safety of nuclear energy and need for safety consciousness. Ex.___

      New to This Edition
      • Discussions of new reactor types including the AP600, ABWR, and SBWR as well as an extensive section on non-US design reactors.

        Provides students with the latest in the technology of the industry. Ex.___

    • The authors have added a discussion on the nuclear Navy and its impact on the development of nuclear energy.
      • Enables a clearer understanding of the importance and use of nuclear power. Ex.___

    • Basic nuclear theory chapters include additional discussions on binding energy and such topics as the semi-empirical mass formula and elementary quantum mechanics.
      • Increases understanding of the origin of nuclear energy. Ex.___

    • Changes in reactor theory sections include a more complete discussion of solutions to the diffusion equation and a more general derivation of the point kinetics equation.
      • Enables students to comprehend the theory. Ex.___

    • Chapter on radiation effects updated to include the latest standards— Both SI and conventional units are discussed and used in examples and problems in this chapter.
      • Prepares students for international interactions. Ex.___

    • Topics in reactor safety now include a complete discussion of the Chernobyl accident and an updated section on TMI and the use of computer codes in safety analysis.
      • Helps readers to appreciate the inherent safety of nuclear energy and need for safety consciousness. Ex.___

        Table of Contents

        (Most chapters end with References</I> andProblems</I>).

        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</I>-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.

        I. Units and Conversion Factors. II. Fundamental Constants and Data. III. Vector Operations in Orthogonal Curvilinear Coordinates. IV. Thermodynamic and Physical Properties. V. Bessel Functions.

        About the Author(s)

        Anthony Baratta is currently a Professor of Nuclear Engineering at The Pennsylvania State University and Director of the Nuclear Safety Center. He received the B.A/B.S. degrees in physics/applied physics from Columbia University in 1968 and the M.S. and Ph.D. degrees in physics from Brown University in 1970 and 1978, respectively. His research interests and contributions include reactor safety, reactor kinetics and physics, and the effects of radiation on materials. He has authored many scientific publications and made numerous presentations. He is an active member of the American Nuclear Society and has appeared on many network television and radio broadcasts as an authority on reactor accidents, including the accident at Three Mile Island.

        Source:

        www.pearsonhighered.com

Lamarsh Errata (3rdEd) - Introduction to Nuclear Engineering, 3rd Edition by

Lamarsh Errata (3rdEd) - Introduction to Nuclear.

Introduction to Nuclear Engineering, 3 rd Edition by J.R. Lamarsh and A.J. Baratta Textbook Errata Pg 6-7. Electron, Proton, and neutron masses are inconsistent with the table in the Appendix. Use the values in the Appendix. Pg 9. Example 2.2 solution equation [ ] ) O ( m ) O ( ) O ( m ) O ( ) O ( m ) O ( 100 1 ) O ( m 18 18 17 17 16 16 ⋅ γ + ⋅ γ + ⋅ γ = Pg 10. The first equation has the exponent missing a minus sign. The mass should be 1.99268 x 10 -23 g. Pg 14. In Eq. (2.13) E should be E total. in order to match the text above it. Regardless, a photon has no rest mass, so kinetic energy equals the total energy. Pg 15. Equation 2.19 is missing the powers on the energy terms. The correct equation is: 2 2 rest total E E hc - = λ Pg 20. Last sentence of second paragraph up from bottom of the page. Should read "Since the daughter nucleus produced in electron capture is the same as the nucleus formed in β + -decay, these two processes often compete with one another." Pg 26. Equation 2.33 is missing a minus sign in the exponent of the last term. Here t b e λ should be written as t b e λ -. Pg 46. In problem 6 the third line of the table is for 238 U not 235 U. Pg 64. The upper value on the ordinate axis of figure 3.4 should be 10 1. not 10 a. Pg 68. The third line of text in example 3.9 should read “is known at” not “is known as”. Pg 69. The brackets in equation 3.28 are incorrect. It should be: ( 29 [ ] 2 2 2 2 sin cos 1 ϑ - + ϑ + = ′ A A E E. Pg 82. Many of the values in Table 3.4 are inconsistent with the tables in the Appendix. Use the values in the Appendix. Pg 92.

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Nuclear Energy - 4th Edition ISBN: 9780080421254

Nuclear Energy Description

This expanded, revised, and updated fourth edition of Nuclear Energy maintains the tradition of providing clear and comprehensive coverage of all aspects of the subject, with emphasis on the explanation of trends and developments. As in earlier editions, the book is divided into three parts that achieve a natural flow of ideas: Basic Concepts, including the fundamentals of energy, particle interactions, fission, and fusion; Nuclear Systems, including accelerators, isotope separators, detectors, and nuclear reactors; and Nuclear Energy and Man, covering the many applications of radionuclides, radiation, and reactors, along with a discussion of wastes and weapons. A minimum of mathematical background is required, but there is ample opportunity to learn characteristic numbers through the illustrative calculations and the exercises. An updated Solution Manual is available to the instructor. A new feature to aid the student is a set of some 50 Computer Exercises, using a diskette of personal computer programs in BASIC and spreadsheet, supplied by the author at a nominal cost. The book is of principal value as an introduction to nuclear science and technology for early college students, but can be of benefit to science teachers and lecturers, nuclear utility trainees and engineers in other fields.

Readership

For students and educators in nuclear, mechanical, electrical and chemical engineering, and practising engineers in the nuclear energy field.

Table of Contents

Preface to the Fourth Edition. Part I Basic Concepts. Energy. Atoms and nuclei. Radioactivity. Nuclear processes. Radiation and materials. Fission. Fusion. Part II Nuclear Systems. Particle accelerators. Isotope separators. Radiation detectors. Neutron heat energy. Breeder reactors. Fusion Reactors. Part III Nuclear Energy and Man. The history of nuclear energy. Biological effects of radiation. Information from isotopes. Useful radiation effects. Reactor safety. Nuclear propulsion. Radiation protection. Radioactive waste disposal. Laws, regulations, and organizations. Energy economics. International nuclear power. Nuclear explosions. The future. Appendix. Index.

8 illus. 155 line drawings, 305 lit. refs.

Details

Language: English Copyright: © Pergamon 1993

Source:

www.elsevier.com

Customer Reviews: Introduction to Nuclear Engineering (3rd Edition)

Customer Reviews

By MF on November 9, 2004

As a textbook for teaching the fundamentals of nuclear engineering, the Lamarsh-Baratta text is horrible. It is riven with errors in the text and examples (and we are using the 3rd edition), the questions are infuriatingly vague at times and in general it does a poor job of explaining an admittedly difficult subject.

Regarding the large numbers of typos, I and my classmates had to search the web for an errata sheet and even then we continue to find errors such as formulae written incorrectly and wrong values for constants.

As for being vague, this text makes you assume many things. A favorite example is a problem early in the text where we not only have to assume neutron energies, we also had to assume fuel type. Then we have to assume energy released per fission and somehow come up with an answer we can be confident in. Ridiculous.

The examples are hit and miss - occasionally they are helpful, an omission I am sure that will be corrected in the 4th edition.

We find ourselves relying on outside texts and materials much of the time to supplement this poorly written textbook.

EDIT ADDED TWO YEARS LATER - Now with perspective from the job world.

After graduating and entering the work force, I mostly stand by the above. I will admit that I do have my copy still with me. It does provide the occasional useful overview of a wide breadth of topics.

I must once again point out the many errata. I still regard it as inexcusable even though I know mistakes do happen - but this is the 3rd edition.

Another thing that would be enormously useful would be if the next edition included units. When teaching this subject, watching how units cancel out or are used can be very, very helpful to undergrad students.

Many students will be forced to use this. I would suggest keeping it on your bookshelf, but if you are supposed to use this in your class, I strongly recommend Nuclear Reactor Engineering by Glasstone and Sesonske as a supplement. The third edition of the Glasstone book can still be found for a reasonable price if you can't afford the most recent edition.

29 people found this helpful

Contains Excellent Information And Several Distractions

First, the caveat to my review: I am probably unique among the reviewers of this book in that I am not a nuclear engineer. I have a strong educational and professional background in chemistry, physics, and math, and have been working on projects involving engineered safety systems and risk management in other technologically advanced industries. I have recently become involved in talks with representatives from the nuclear industry. For my own preparation I undertook the long hard slog through the Lamarsh-Baratta book, "Introduction to Nuclear Engineering" (Third Edition) to help me grasp background information and concepts in this field. Although I was sometimes initially unclear about the use of units (barns, dollars, etc.) and nomenclature (meat, safe shutdown earthquake, etc.) I generally found the text to eventually explain them adequately. One critique is that at some points in the text the authors use terminology freely without first defining it, only to define it much later. I found this and the relatively large number of typographical errors to be distracting.

This is clearly a very complex subject, and would no doubt be helped by good classroom instruction. Nonetheless, I still found considerable value in the book. I liked chapter seven, "The Time-Dependent Reactor" particularly well, and especially found sections 7.3 and 7.5 "Control Rods and Chemical Shim" and "Fission Product Poisoning" to be enlightening. I found the commentary on reactor stability and the explanation of post-shutdown Xenon-135 buildup and reactor deadtime extremely helpful. I also found section 7.6 on incore fuel management useful.

From my experience in aviation (where it is a common parameter), I enjoyed the discussion of the utility of the Reynolds number in section 8.4, and found the ensuing discussions of turbulent flow, liquid metals, and boiling heat transfer to be fascinating. My safety systems background is primarily in aviation, where it is stressed that every design is a compromise: I was pleased to see the same acknowledged on p. 455 by Bill Minkler (who now writes the "Backscatter" commentary for "Nuclear News") with his quote that reactor design is "the art of compromise."

I was pleased with chapters nine ("Radiation Protection") and eleven ("Reactor Licensing, Safety, and the Environment"), which are the most directly applicable to me. The concept of "Relative Biological Effectiveness" is well covered beginning on p. 472, and the discussions of radiation protection are helpful. I found the section dealing with deterministic versus stochastic effects of radiation on pp. 479-480 to be helpful, and thought the glossary of radiation protection on pp. 539-542 to be a valuable reference. I wanted to better understand the principles of Monte Carlo analysis, which is covered in chapter ten, and while much of the discussion was helpful, it was a bit more general than I had expected.

The overview of reactor licensing in chapter eleven is quite helpful, although becoming a bit dated. The discussion of multiple barriers to prevent to escape of radiation begins on p. 623 and provides an excellent general overview to the safety systems involved at a reactor site. Section 11.4 ("Dispersion of Effluents") was excellent overall, with plume formation and diffusion of effluents well covered for all Pasquill conditions (except G). This was an area new to me, as I have minimal meteorological knowledge, and I found the qualitative explanations and illustrations to be excellent, although the mathematical reasoning was at some points a bit hard to follow.

The discussion of Design Basis Accidents (and particularly LOCA scenarios) beginning on p. 681 is excellent, as is the recap of the Three Mile Island and Chernobyl accidents which follow. I was pleased to see the introduction to risk management beginning on p. 711, which discusses 10CFR50.34a requiring operators to keep radioactive materials in effluents "as low as reasonably achievable." Oddly, the book the fails to name the acronym that logically follows from this (ALARA, of course) or discuss its use in the contemporary nuclear community to any significant degree.

There is a lot of great content here, and while I am sure that I missed some of the more intricate mathematical nuances of the book, I think it was helpful to me overall. The book is sometimes a bit unclear, and some of the mathematical reasoning seems a bit fuzzy. A bigger complaint is that each chapter has numerous problems at the end, yet there is no answer key to determine if you did the problem correctly.

I don't claim to have as much experience in the field as the vast majority of people who will read and review this book, but I do believe that overall the book, while not perfect, gives a good introduction to the subject, and will serve as a valuable reference in the future.

10 people found this helpful

Not as bad as some claim, but not as good either

I have used this book effectively for the past three years of my Nuclear Engineering Graduate degree and have a fond place for it in my heart. Admittedly there are better texts out there and the book has many typos and errors, but the advantage it has is the text is written so straight forward and plainly that most, if not all of the errors, can be found readily by the reader.

Overall, I recommend this book to someone who is new to the nuclear engineering field and is uncertain where to start with his or her study of the subject. Once the foundation has been laid by the material presented in this text the reader is ready to pursue other books, which may be more accurate, but not nearly as clear in their presentation of concepts. (such as Duderstadt and Hamilton.)

10 people found this helpful

Excelent book for the non-nuclear engineer

By Gonzalo on May 18, 1998

A great book to self-teach nuclear engineering. Oriented to the advanced student of physics, or the engineer. Starts with a review of particle physics and modern physic basics, ending in the design of nuclear reactors, safety procedures and effects of radiation on living organisms.

10 people found this helpful

If you get the paperback edition, be aware that it is not technically supposed to be sold in the US (it says so in the red triangle in the upper left-hand corner) and that it is lacking the tables and charts in the back.
And, of course, like everyone else has said, a lot of the actual numbers in the book are wrong.

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Horrible explanations on how to do homework because there are.

By CC on July 4, 2014

Horrible explanations on how to do homework because there are no good examples. However, the overall content of the book is impressive. Many changes need to be made as is shown by the errata that goes with it found online.

One person found this helpful

By Lucchese on December 26, 2007

I read the book cover-to-cover. For a third edition, it has an astounding number of typos and errors - dozens per chapter - many math blunders - a few conceptual mistakes. It's fairly distracting from the material. The reader is constantly second-guessing the text - looking for the next mistake which is never far away. There's something dysfunctional about this publishing team to continue ignoring the huge number of errors now into this third edition. (The 'errata' list at Prentice-Hall website is obsolete. Those have already been corrected in our copy, printed 2005. Their list says nothing about the many errors we observed.)

4 people found this helpful

Errors and conceptual issues

This book could be worse, but it has A LOT of room for improvement. I took a nuclear engineering course using this book. Both the professor and the other students expressed frustration with this book, particularly with the questions at the end of each chapter, which usually require a lot of supplementary material to complete, or are impossible to answer altogether.

The biggest problem is all the errors. Oftentimes, how a particular calculation is to be performed is only demonstrated in an example. The examples frequently make mistakes in dimensional analysis, or do not mention dimensions at all. At least one example in each chapter also has some significant algebra mistake. With the absence of units shown in the calculation it is extremely difficult to learn the correct method from some of these examples.

Some of the "problems" in the book are very difficult. They are often impossible to answer without a good deal of information and prior knowledge on the topic. "Introduction" may be misleading; to understand this textbook well it is necessary to have a good background in particle physics and chemical/process engineering.

The section on heat transfer treats the topic very clumsily; although the methods described are not wrong, they are very awkward and roundabout. The treatment is not very in depth, but is very unusual and can be confusing. It makes me suspect that the other confusing topics in the book are also over-complications, but of topics I am less familiar with, so I don't already know better ways to describe the topic.

Another infuriating mistake is that the author describes steady state as "equilibrium", which are not the same thing. This may seem like a minor point but for process engineering it is important to distinguish between the two, and this text consistently states something is "at equilibrium" when it actually should be saying that the system has reached a steady state.

Overall, I would not recommend this book. It is error-ridden and confusing. Unlabeled axes, unspecified units, and unnecessary variable substitutions and difficult to read charts are all features of this book. The best chapter I found in it was the one describing different reactor types, it was a nice brief overview, although it is starting to become slightly dated.

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Highly recommend for any engineering student or anyone who is interested.

Currently using this text for my Nuclear Reactor Theory and Design course. Very informative text with clear descriptions of underlying physical principles. Highly recommend for any engineering student or anyone who is interested in the subject matter.

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By Tassos on April 6, 2004

This is the best introductory book in nuclear engineering I have ever encountered in my life. The late professor John Lamarsh had the unique ability to convey information to his students in an unbelievably straight forward manner. This book reflects his teaching approach, completely. If you are studying nuclear engineering it should be your first stop.
If you are a (non-nuclear) engineering professional or student and really need to communicate with nuclear engineers or comprehend concepts of nuclear applications you have to study this book. Finally, if you are preparing for your qualifying examinations, it is an absolute must.
The book is a masterpiece of pedagogical methodology in nuclear engineering. It will make you feel comfortable with the intricacies of nuclear reactor theory, within a short period of time. In addition, you will be introduced to solid thermodynamic concepts that are coupled to reactor theory. Equal teaching importance is given to nuclear licensing, radiation physics, and shielding.
Essentially, this book covers the whole spectrum of basic nuclear engineering.

5 people found this helpful

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PSU Continuing and Distance Education

NucE 497 Introduction to Nuclear Engineering

This course is designed as an intensive semester-long course providing introduction to nuclear engineering (NucE) to the undergraduate co-op students, and to graduate students with non-NucE background, and to returning students. After successfully completing this course, undergraduate students will be able to effectively follow the regular NucE curriculum.

Dr. Justin Watson
RESEARCH ASSOCIATE AND ASSISTANT PROFESSOR OF NUCLEAR ENGINEERING

3330B G. THOMAS WATER TUNNEL

University Park, PA 16802

J. R. Lamarsh and Anthony Baratta,

"Introduction to Nuclear Engineering, 3rd Edition"

J. K. Shults and R. E. Faw,
�Fundamentals of Nuclear Science and Engineering�, Second Edition,
Taylor & Francis Group, 2007


The enrollment process is:

Contact the the Office of Continuing and Distance Education for admission into the course.
  • Complete and submit the Registration Form via mail, fax, or in person. See the Registration Page .

  • Office for Disability Services
    Penn State welcomes students with disabilities into the University�s educational programs. If you have a disability‐related need for reasonable academic adjustments in this course, contact the Office for Disability Services (ODS) at 814‐863‐1807 (V/TTY). For further information regarding ODS, please visit the Office of Disability Services website at http://equity.psu.edu/ods

    In order to receive consideration for course accommodations, you must contact ODS and provide documentation (see the documentation guidelines at http://equity.psu.edu/ods/guidelines. If the documentation supports the need for academics adjustments, ODS will provide a letter identifying appropriate academics adjustments. Please share this letter and discuss the adjustments with your instructor as early in the course as possible. You must contact ODS and request academic adjustment letters at the beginning of each semester.

    � Penn State University
    Office of Continuing and Distance Education in Engineering
    301-A Engineering Unit C
    University Park, PA 16802
    Phone: (814) 865-7643 Fax: (814) 865-3969
    E-mail: masdo@engr.psu.edu

    Source:

    www.engr.psu.edu

    NE 150

    NE 150

    Prerequisite Knowledge and/or Skills:

    • The course uses the following knowledge and skills from prerequisite and lower-division courses:
    • solution of linear, first and second order differential equations.
    • vector calculus, special functions (Bessel functions, Exponential integrals).
    • basic nuclear physics.
    • basic interactions of radiation with matter, and concept of cross sections.
    • review those aspects of neutron interactions with matter that are pertinent to understanding the establishment of a chain-reaction and of the neutron space- and energy-distribution in the nuclear reactor core.
    • show how the complex neutron transport and slowing-down processes can be described by simple, though approximate, analytical models.
    • develop the students' insight and understanding of neutron-related phenomena in nuclear reactors.
    • show how to quantify the space-dependence, energy-dependence and time-dependence of the neutron population.
    • acquaint the students with the neutronic design considerations and design constraints of nuclear reactors.
    • illustrate, with examples drawn from various reactor and other neutronic systems, how nuclear reactor theory can be used to quantify the behavior of these system under various conditions.
    • acquaint students with the specific features of different types of nuclear reactors, with particular emphasys on light water reactors (LWRs).
    • calculate spectrum-averaged microscopic cross-sections for thermal neutrons, macroscopic cross-sections for a single isotope and for a mixture of isotopes, reaction probabilities, mean-free-path, mean time for collision, mean energy loss per elastic collision.
    • calculate spectrum-averaged microscopic cross-sections for thermal neutrons, access computerized data files of 0.0253eV cross-sections as well as of Maxwellian averaged cross-sections, of fission spectrum averaged cross-sections and of resonance integrals.
    • calculate the slowing-down time, the diffusion time, mean distance of displacement while slowing-down, mean distance of displacement while diffusing as a thermal neutron.
    • write mathematical formulations (equations) describing neutron balances (gains and losses) in multiplying systems: the equation of continuity, criticality conditions, the point reactor kinetics equations and the rate equations for changes in nuclide densities.
    • solve the one-group and two-groups steady state diffusion equation for simplified systems, both non-multiplying and multiplying, as well as for bare and reflected systems; find the spatial neutron and associated power distributions.
    • calculate the magnitude of the neutron flux from published information on the nuclear reactor (total power and fuel inventory; specific power; power density and lattice geometry and composition).
    • calculate the critical concentration, critical mass and dimensions for bare and reflected cores.
    • estimate the magnitude of the four-factors and of the infinite-multiplication-factor in heterogeneous systems.
    • calculate the asymptotic reactor period resulting from introduction of positive and negative reactivity and calculate the reactivity that need be introduced in order to change the reactor power level by a given factor in a given time.
    • estimate the reactivity effect associated with the buildup of fission products, with the change in fuel temperature and of coolant temperature, and with fuel burnup; calculate the reactivity effect of a given concentration of a thermal neutron absorber uniformly distributed across the core.
    • calculate the change in concentration of fission products as a function of the reactor operating time and as a function of the reactor shutdown time.
    • solve the rate-equations for the change in the concentration of different isotopes in an operating reactor.
    • General description of nuclear reactors and statistics about worldwide nuclear power production.
    • Review of the basic of neutron interactions: possible type of interactions; consequences of these interaction; interaction probability; microscopic and macroscopic cross sections, cross-section systematics; cross-section data.
    • Slowing-down of neutrons: elastic scattering mechanics; energy loss; average logarithmic energy decrement; slowing-down time; effect of inelastic scattering; collision and slowing-down densities; resonance absorption.
    • Fission chain reaction: chain reaction in thermal and fast systems; the four- and six-factor formulas; nuclear fuels; conversion and breeding.
    • Neutron spectra: thermal equilibrium; typical neutron spectrum in thermal and fast reactors; effective spectrum averaged cross-sections; resonance integrals.
    • Introduction to neutron diffusion theory: neutron flux and current, equation of continuity, Fick's law, transport corrections; the diffusion equation for monoenergetic neutrons, boundary conditions; elementary solutions of the steady-state diffusion equation, solutions for multiplying media, multi-group diffusion equations; solution of the two-group diffusion equation.
    • Nuclear reactor theory: one-group reactor equation, criticality conditions; effect of reflectors; determination of critical concentration, dimension and mass; heterogeneity effects: fuel lumping and control-absorber lumping; calculation of thermal utilization, resonance escape probability, and fast fission factor.
    • Point reactor kinetics: point reactor kinetics equations; prompt neutron lifetime; effect of delayed neutrons; definition and units of reactivity, the asymptotic reactor period versus changes in reactivity.
    • Reactivity variations in operating reactors: effects of fuel and coolant temperature change; effect of coolant voiding; effect of fission products; effect of fuel depletion; BOL excess reactivity requirements for different reactor types.
    • Methods for compensation of reactivity variations: control rods; coolant inlet temperature; chemical shim; burnable poison; in-core fuel management.

    Textbook(s) and/or Other Required Materials:

    Contribution of Course to Meeting the Professional Component:

    • This course contributes primarily to the students' knowledge of engineering topics, and does provide design experience.
    • Introduction to Nuclear Reactor Theory provides the students with the understanding of the phenomena that take place in fission reactors and with the understanding of the nuclear reactor design requirements. This course provides the students with tools for, and experience in simplified design and analysis of nuclear reactor cores. It also gives the students an insight in the neutronics behavior of other systems such as source-driven subcritical systems, fusion reactor blankets and facilities for medical applications.

    Relationship of Course to Degree Program Objectives:

    • This course primarily serves students in the department. The information below describes how the course contributes to the undergraduate program objectives.
    • This course contributes to the NE program objectives by providing education in an area (nuclear reactor theory) that is of central importance for a career in nuclear engineering.

    Assessment of Student Progress Toward Course Objectives:

    Source:

    www.nuc.berkeley.edu

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