A closer look at neutrons in nuclear and radiological engineering / V.P. Singh, H.R. Vega-Carrillo and Kulwinder Singh Mann, editors.

Format:

Book

Contributor:

Singh, V. P., editor.

Vega-Carrillo, H. R., editor.

Mann, Kulwinder Singh, editor.

Series:

Physics research and technology.

Physics Research and Technology

Language:

English

Subjects (All):

Neutrons.

Physical Description:

1 online resource (252 pages)

Place of Publication:

Hauppauge, New York : Nova Science Publishers, [2021]

Summary:

"The neutron is an unstable nucleon outside the atomic nucleus; its mass is approximately 0.0014 times higher than the proton's mass and it plays an essential role in the atomic nucleus's stability. The neutron does not have an electric charge and interacts with matter causing numerous reactions. The above properties make the neutron essential in several areas. In nuclear power production, for instance, the neutron combined with the moderator plays a critical role. This book is a collection of works related to the neutron and its applications. Each chapter of this book's content is self-contained and is derived from the experience and research carried out by the authors. The book describes each aspect of neutrons ranging from their essential characteristics to their applications. Chapters of this book concern topics including the description of neutron characteristics, the challenge of neutron dosimetry, the ambient dose equivalent due to cosmic neutrons, the use of neutrons as an analytical tool through neutron activation analysis, the absorbed dose response of natural minerals which also have thermoluminescent features, and the use of neutrons in medicine to treat cancer and rheumatoid arthritis. The book also discusses topics such as neutron attenuation by super-alloys, neutron production in radiotherapy with electrons, the use of neutrons to detect explosives, and cloud computing technology for neutron dosimetry and spectrometry. This book would be handy for scientists, engineers, researchers, students, and practitioners in neutron studies and applications"-- Provided by publisher.

Contents:

Intro

Contents

Preface

Chapter 1

Neutron Features: The Importance of Neutrons

1. Introduction: A Brief Historical Context

2. The Importance of Neutrons in the Atomic Nuclei

3. Neutron Interaction and Transport through Matter

3.1. Neutron Interaction: Nuclear Reactions

3.2. Neutron Transport through Matter

3.2.1. Deterministic Methods

3.2.2. Stochastic Methods

4. Brief Introduction to Neutron Dosimetry

Participants

References

Chapter 2

Neutron Dosimetry

Abstract

Introduction

Conclusion

Chapter 3

Ambient Dose Equivalent Due to Cosmic Neutrons

Cosmic Radiation

Neutrons in the Environment

Neutron Monitoring

Cosmic Neutrons

Ambient Dose Equivalent Due to Neutrons

Materials and Methods

Results

Chapter 4

Principles and Uses of Neutron Activation

Nuclear Reactors

Neutron Generators

Linear Accelerators (Neutrons Generated as Secondary Reactions)

Isotopic Sources

Spontaneous Fission

Neutron Activation Analysis (NAA)

Activation Analysis (DGNAA &amp

PGNAA)

Instrumental Neutron Activation Analysis (INAA)

Radiochemical Neutron Activation Analysis (RNAA)

Photon Activation Analysis (PAA)

Fast Neutron Activation Analysis (FNAA)

Charged Particle Activation Analysis (CPAA)

Thermal Neutron Activation Analysis (TNAA)

Epithermal Neutron Activation Analysis (ENAA)

Scintillation Materials

Chapter 5

Absorbed Dose Response to Neutrons of Quartz and Mexican Onyx

Neutrons

Shielding

Natural Minerals

Mexican Onyx (CaCO3)

Quartz (SiO2)

Absorbed Dose Response Calculations

Neutron Response of Mexican Onyx and Quartz

Chapter 6

Neutrons in Medicine.

Abstract

Uses of Ionizing Radiation in Medicine

Neutron Production and Interaction with Matter

The Elastic Dispersion or Nuclear Reaction (n, n)

The Inelastic Scattering (n, n '), (n, n'γ)

Radioactive Capture (n, γ)

Capture Reactions (n, αp), (n, 2n), (n, d), (n, p), (n, α), (n, t)

Fission Reaction (n, f)

Classification of Neutrons

Thermal Neutrons

Epithermal Neutrons

Fast Neutrons

Magnitudes in Radiation Protection

Exposure (X)

Kerma in Air (K)

Absorbed Dose (D)

Equivalent Dose (H)

Effective Dose (E)

Boron Neutron Capture Therapy (BNCT)

LET

Relative Biological Efficacy (RBE)

Chapter 7

Neutron Radiation Attenuation Characteristics of Rhenium- Boron- Iron New Superalloys

Material and Methods

Neutron Shielding Theory

Cross Section

Geant4 Monte Carlo Simulation

Sample Preparation

Results and Discussion

Fast Neutron Attenuation Parameters

Neutron Radiation Dose Measurements

Chapter 8

Neutron Production in Radiotherapy Treatment with Monoenergetic Electrons and Patient Received Dose

Methods

Chapter 9

Explosives Detection Using Neutrons

Chapter 10

Neutron Spectrometry and Dosimetry with Application Virtualization, an Industry 4.0 Cloud Computing Technology

Neutron Spectrometry from BSS

The Problem of Neutron Spectrometry

Approaches and Codes for Neutron Spectrometry

Neutron Spectrometry Evolution

Server Virtualization

Application Virtualization

eButterfly Unfolding Code Executed with AV Technology

Discussion and Conclusion

Acknowledgments

References.

About the Editors

Index

Blank Page.

Notes:

Description based on print version record.

ISBN:

1-5361-9772-6

OCLC:

1255234159