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  • 1
    Online Resource
    Online Resource
    Monte Carlo N-Particle Simulations for Nuclear Detection and Safeguards : An Examples-Based Guide for Students and Practitioners. (2022)
    Cham :Springer International Publishing AG,
    Details
    UID:
    almahu_9949419766302882
    Format: 1 online resource (316 pages)
    ISBN: 3-031-04129-1
    Content: This open access book is a pedagogical, examples-based guide to using the Monte Carlo N-Particle (MCNPª) code for nuclear safeguards and non-proliferation applications. The MCNP code, general-purpose software for particle transport simulations, is widely used in the field of nuclear safeguards and non-proliferation for numerous applications including detector design and calibration, and the study of scenarios such as measurement of fresh and spent fuel. This book fills a gap in the existing MCNP software literature by teaching MCNP software usage through detailed examples that were selected based on both student feedback and the real-world experience of the nuclear safeguards group at Los Alamos National Laboratory. MCNP input and output files are explained, and the technical details used in MCNP input file preparation are linked to the MCNP code manual. Benefiting from the authors' decades of experience in MCNP simulation, this book is essential reading for students, academic researchers, and practitioners whose work in nuclear physics or nuclear engineering is related to non-proliferation or nuclear safeguards. Each chapter comes with downloadable input files for the user to easily reproduce the examples in the text.
    Note: Table of contents: Contents 4 Introduction 8 Section 1: Basic Concepts 26 1.1.8 Lattice Geometries 53 1.2.6 Electron stopping powers for coupled photon and electron problems . 57 1.2.7 Data and models for Ions and Charged Particles 61 1.2.8 Additional data diagnostics and recommendations 62 1.3 Sources 63 1.3.1 SDEF Fixed Sources .63 1.3.2 SDEF Source Distributions 66 1.3.3 SDEF Dependent Distributions: DS 69 1.3.4 Criticality Sources 71 1.3.5 Surface Source Read and Write (SSR, SSW) 77 1.3.6 Checking sources 87 1.4 Output and Tallies 87 1.4.1 Output Files 87 1.4.2 MCNP Estimators and Tally Types 93 DRAFT 5 1.4.3 Basic Tally Format 95 1.4.4 Special Tally Treatments 111 1.4.5 Pulse-Height Tallies. 128 1.4.6 Point Detectors and Next-Event Estimators 134 1.5 Plotting 143 1.5.1 Geometry Plotting and Command Files143 1.5.2 Cross Section plotting 145 1.5.3 Tally Plotting 150 1.5.4 Mesh, Radiography, and Ring Tallies 167 1.6 Statistics and Convergence 186 Section 2: Examples for nuclear safeguards applications 198 2.1 Example 1: Fuel Assembly in Water Tank 198 2.1.1 Description 198 2.1.2 Geometry description 203 2.1.3 Other data: sources, materials, tallies, and more 204 2.1.4 MCNP Output 206 2.2 Example 2: Coincidence Counter with F4 and F8 Tallies for Coincidence and Multiplicity Counting Rates 207 2.2.1 Description 207 2.2.2 Materials 212 2.2.3 Source 212 2.2.4 Tallies 213 2.2.5 Warning Messages 214 2.2.6 Results 216 2.2.6A: From the Point Model. 216 2.2.6B: Rates Calculated without Point Model assumptions 221 2.3 Gamma pulse height (to be completed) 227 2.4 Active Neutron Example: Cf Shuffler. 231 2.4.1 Description and input file. 231 2.4.2 Results 234 Section 3: Examples of Advanced Concepts 240 Section 3.1 Variance Reduction 240 3.1.1 Introduction 240 DRAFT 6 3.1.2 Multigroup Weight Windows and Time Splitting: Lead Slowing Down Spectrometer 242 3.1.2.1 Input File Notes 253 3.1.2.2 Variance Reduction Step 1: simplify problem and add weight window generator 256 3.1.2.3 Iteration 2 .261 3.1.2.4 Additional iterations 263 3.1.2.5 Cylindrical Mesh Weight Window Summary 267 3.1.3 Cell-based weight windows for the Lead Slowing Down Spectrometer 271 3.1.4 Time splitting 277 3.1.5 Variance Reduction for the Cf Shuffler. 280 3.1.5.1 Cf Shuffler modified input 280 3.1.5.2 Particle production bias, time splitting, and windows 285 3.1.5.3 Analysis of Cf Shuffler Variance Reduction 288 3.2 DXTRAN and Other Capabilities for Distributed Source Problems 288 3.2.1 UF6 Cask Model 290 3.2.2 DXTRAN 300 3.2.3 Source Position Biasing 307 3.2.4 Best Single Detector Solution 310 3.3 Neutron Detector Operation in More Detail. 318 3.3.1 Introduction 318 (i) Make reaction products (model, data) and recoil nuclei 318 (ii) Track created particles in real gas composition 321 (iii) Tally energy deposition of particles in active volume (F8 CAP EDEP for coincidence/multiplicity counting) 322 Examples 322 3He detector Pulse Height. 322 3He Detector Coincidence Calculation 324 10B-lined detectors 325 References 332 Section 4: Additional Topics 332 4.1 Troubleshooting or "How can I be confident in the results?" 332 4.1.1 Geometry and Materials. 333 4.1.2 Detector modelling 334 DRAFT 7 4.1.3 Source modelling 334 4.1.4 Sample modelling 335 4.1.5 Tracking limitations 335 4.1.6 Nuclear Data 335 4.1.7 Statistics 336 4.1.8 User .337 4.1.9 Summary and Conclusions - What to do?. 337 4.2.1 Analysis of Delayed Neutron Production 338 4.2.2 Comparison of Table Physics vs Model Physics 342 5 References and Bibliography. 354 6 Table of Figures 355.
    Additional Edition: ISBN 3-031-04128-3
    Language: English
    URL: Volltext  (kostenfrei)
    URL: Volltext  (kostenfrei)
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  • 2
    Online Resource
    Online Resource
    Monte Carlo N-Particle Simulations for Nuclear Detection and Safeguards : An Examples-Based Guide for Students and Practitioners (2022)
    Cham :Springer International Publishing :
    Details
    UID:
    almahu_9949371888302882
    Format: XV, 307 p. 106 illus., 82 illus. in color. , online resource.
    Edition: 1st ed. 2022.
    ISBN: 9783031041297
    Content: This open access book is a pedagogical, examples-based guide to using the Monte Carlo N-Particle (MCNP®) code for nuclear safeguards and non-proliferation applications. The MCNP code, general-purpose software for particle transport simulations, is widely used in the field of nuclear safeguards and non-proliferation for numerous applications including detector design and calibration, and the study of scenarios such as measurement of fresh and spent fuel. This book fills a gap in the existing MCNP software literature by teaching MCNP software usage through detailed examples that were selected based on both student feedback and the real-world experience of the nuclear safeguards group at Los Alamos National Laboratory. MCNP input and output files are explained, and the technical details used in MCNP input file preparation are linked to the MCNP code manual. Benefiting from the authors' decades of experience in MCNP simulation, this book is essential reading for students, academic researchers, and practitioners whose work in nuclear physics or nuclear engineering is related to non-proliferation or nuclear safeguards. Each chapter comes with downloadable input files for the user to easily reproduce the examples in the text.
    Note: Chapter 1: Introduction -- Chapter 2: Basic Concepts -- Chapter 3: Examples for Nuclear Safeguards Applications -- Chapter 4: Examples of Advanced Concepts -- Chapter 5: Additional Topics.
    In: Springer Nature eBook
    Additional Edition: Printed edition: ISBN 9783031041280
    Additional Edition: Printed edition: ISBN 9783031041303
    Additional Edition: Printed edition: ISBN 9783031041310
    Language: English
    DOI: 10.1007/978-3-031-04129-7
    URL: https://doi.org/10.1007/978-3-031-04129-7
    URL: kostenfrei
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    HU Berlin
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  • 3
    Online Resource
    Online Resource
    Monte Carlo N-Particle Simulations for Nuclear Detection and Safeguards : An Examples-Based Guide for Students and Practitioners. (2022)
    Cham :Springer International Publishing AG,
    Details
    UID:
    almahu_9949420497402882
    Format: 1 online resource (316 pages)
    ISBN: 9783031041297
    Additional Edition: Print version: Hendricks, John S. Monte Carlo N-Particle Simulations for Nuclear Detection and Safeguards Cham : Springer International Publishing AG,c2022 ISBN 9783031041280
    Language: English
    Keywords: Electronic books.
    URL: Click to View
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    HU Berlin
  • 4
    Online Resource
    Online Resource
    Monte Carlo N-Particle Simulations for Nuclear Detection and Safeguards : An Examples-Based Guide for Students and Practitioners. (2022)
    Cham :Springer International Publishing AG,
    Details
    UID:
    edoccha_9960862305002883
    Format: 1 online resource (316 pages)
    ISBN: 3-031-04129-1
    Content: This open access book is a pedagogical, examples-based guide to using the Monte Carlo N-Particle (MCNPª) code for nuclear safeguards and non-proliferation applications. The MCNP code, general-purpose software for particle transport simulations, is widely used in the field of nuclear safeguards and non-proliferation for numerous applications including detector design and calibration, and the study of scenarios such as measurement of fresh and spent fuel. This book fills a gap in the existing MCNP software literature by teaching MCNP software usage through detailed examples that were selected based on both student feedback and the real-world experience of the nuclear safeguards group at Los Alamos National Laboratory. MCNP input and output files are explained, and the technical details used in MCNP input file preparation are linked to the MCNP code manual. Benefiting from the authors' decades of experience in MCNP simulation, this book is essential reading for students, academic researchers, and practitioners whose work in nuclear physics or nuclear engineering is related to non-proliferation or nuclear safeguards. Each chapter comes with downloadable input files for the user to easily reproduce the examples in the text.
    Note: Table of contents: Contents 4 Introduction 8 Section 1: Basic Concepts 26 1.1.8 Lattice Geometries 53 1.2.6 Electron stopping powers for coupled photon and electron problems . 57 1.2.7 Data and models for Ions and Charged Particles 61 1.2.8 Additional data diagnostics and recommendations 62 1.3 Sources 63 1.3.1 SDEF Fixed Sources .63 1.3.2 SDEF Source Distributions 66 1.3.3 SDEF Dependent Distributions: DS 69 1.3.4 Criticality Sources 71 1.3.5 Surface Source Read and Write (SSR, SSW) 77 1.3.6 Checking sources 87 1.4 Output and Tallies 87 1.4.1 Output Files 87 1.4.2 MCNP Estimators and Tally Types 93 DRAFT 5 1.4.3 Basic Tally Format 95 1.4.4 Special Tally Treatments 111 1.4.5 Pulse-Height Tallies. 128 1.4.6 Point Detectors and Next-Event Estimators 134 1.5 Plotting 143 1.5.1 Geometry Plotting and Command Files143 1.5.2 Cross Section plotting 145 1.5.3 Tally Plotting 150 1.5.4 Mesh, Radiography, and Ring Tallies 167 1.6 Statistics and Convergence 186 Section 2: Examples for nuclear safeguards applications 198 2.1 Example 1: Fuel Assembly in Water Tank 198 2.1.1 Description 198 2.1.2 Geometry description 203 2.1.3 Other data: sources, materials, tallies, and more 204 2.1.4 MCNP Output 206 2.2 Example 2: Coincidence Counter with F4 and F8 Tallies for Coincidence and Multiplicity Counting Rates 207 2.2.1 Description 207 2.2.2 Materials 212 2.2.3 Source 212 2.2.4 Tallies 213 2.2.5 Warning Messages 214 2.2.6 Results 216 2.2.6A: From the Point Model. 216 2.2.6B: Rates Calculated without Point Model assumptions 221 2.3 Gamma pulse height (to be completed) 227 2.4 Active Neutron Example: Cf Shuffler. 231 2.4.1 Description and input file. 231 2.4.2 Results 234 Section 3: Examples of Advanced Concepts 240 Section 3.1 Variance Reduction 240 3.1.1 Introduction 240 DRAFT 6 3.1.2 Multigroup Weight Windows and Time Splitting: Lead Slowing Down Spectrometer 242 3.1.2.1 Input File Notes 253 3.1.2.2 Variance Reduction Step 1: simplify problem and add weight window generator 256 3.1.2.3 Iteration 2 .261 3.1.2.4 Additional iterations 263 3.1.2.5 Cylindrical Mesh Weight Window Summary 267 3.1.3 Cell-based weight windows for the Lead Slowing Down Spectrometer 271 3.1.4 Time splitting 277 3.1.5 Variance Reduction for the Cf Shuffler. 280 3.1.5.1 Cf Shuffler modified input 280 3.1.5.2 Particle production bias, time splitting, and windows 285 3.1.5.3 Analysis of Cf Shuffler Variance Reduction 288 3.2 DXTRAN and Other Capabilities for Distributed Source Problems 288 3.2.1 UF6 Cask Model 290 3.2.2 DXTRAN 300 3.2.3 Source Position Biasing 307 3.2.4 Best Single Detector Solution 310 3.3 Neutron Detector Operation in More Detail. 318 3.3.1 Introduction 318 (i) Make reaction products (model, data) and recoil nuclei 318 (ii) Track created particles in real gas composition 321 (iii) Tally energy deposition of particles in active volume (F8 CAP EDEP for coincidence/multiplicity counting) 322 Examples 322 3He detector Pulse Height. 322 3He Detector Coincidence Calculation 324 10B-lined detectors 325 References 332 Section 4: Additional Topics 332 4.1 Troubleshooting or "How can I be confident in the results?" 332 4.1.1 Geometry and Materials. 333 4.1.2 Detector modelling 334 DRAFT 7 4.1.3 Source modelling 334 4.1.4 Sample modelling 335 4.1.5 Tracking limitations 335 4.1.6 Nuclear Data 335 4.1.7 Statistics 336 4.1.8 User .337 4.1.9 Summary and Conclusions - What to do?. 337 4.2.1 Analysis of Delayed Neutron Production 338 4.2.2 Comparison of Table Physics vs Model Physics 342 5 References and Bibliography. 354 6 Table of Figures 355.
    Additional Edition: ISBN 3-031-04128-3
    Language: English
    Library Location Call Number Volume/Issue/Year Availability
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    Online Resource
    Charité
  • 5
    Online Resource
    Online Resource
    Monte Carlo N-Particle Simulations for Nuclear Detection and Safeguards : An Examples-Based Guide for Students and Practitioners. (2022)
    Cham :Springer International Publishing AG,
    Details
    UID:
    edocfu_9960862305002883
    Format: 1 online resource (316 pages)
    ISBN: 3-031-04129-1
    Content: This open access book is a pedagogical, examples-based guide to using the Monte Carlo N-Particle (MCNPª) code for nuclear safeguards and non-proliferation applications. The MCNP code, general-purpose software for particle transport simulations, is widely used in the field of nuclear safeguards and non-proliferation for numerous applications including detector design and calibration, and the study of scenarios such as measurement of fresh and spent fuel. This book fills a gap in the existing MCNP software literature by teaching MCNP software usage through detailed examples that were selected based on both student feedback and the real-world experience of the nuclear safeguards group at Los Alamos National Laboratory. MCNP input and output files are explained, and the technical details used in MCNP input file preparation are linked to the MCNP code manual. Benefiting from the authors' decades of experience in MCNP simulation, this book is essential reading for students, academic researchers, and practitioners whose work in nuclear physics or nuclear engineering is related to non-proliferation or nuclear safeguards. Each chapter comes with downloadable input files for the user to easily reproduce the examples in the text.
    Note: Table of contents: Contents 4 Introduction 8 Section 1: Basic Concepts 26 1.1.8 Lattice Geometries 53 1.2.6 Electron stopping powers for coupled photon and electron problems . 57 1.2.7 Data and models for Ions and Charged Particles 61 1.2.8 Additional data diagnostics and recommendations 62 1.3 Sources 63 1.3.1 SDEF Fixed Sources .63 1.3.2 SDEF Source Distributions 66 1.3.3 SDEF Dependent Distributions: DS 69 1.3.4 Criticality Sources 71 1.3.5 Surface Source Read and Write (SSR, SSW) 77 1.3.6 Checking sources 87 1.4 Output and Tallies 87 1.4.1 Output Files 87 1.4.2 MCNP Estimators and Tally Types 93 DRAFT 5 1.4.3 Basic Tally Format 95 1.4.4 Special Tally Treatments 111 1.4.5 Pulse-Height Tallies. 128 1.4.6 Point Detectors and Next-Event Estimators 134 1.5 Plotting 143 1.5.1 Geometry Plotting and Command Files143 1.5.2 Cross Section plotting 145 1.5.3 Tally Plotting 150 1.5.4 Mesh, Radiography, and Ring Tallies 167 1.6 Statistics and Convergence 186 Section 2: Examples for nuclear safeguards applications 198 2.1 Example 1: Fuel Assembly in Water Tank 198 2.1.1 Description 198 2.1.2 Geometry description 203 2.1.3 Other data: sources, materials, tallies, and more 204 2.1.4 MCNP Output 206 2.2 Example 2: Coincidence Counter with F4 and F8 Tallies for Coincidence and Multiplicity Counting Rates 207 2.2.1 Description 207 2.2.2 Materials 212 2.2.3 Source 212 2.2.4 Tallies 213 2.2.5 Warning Messages 214 2.2.6 Results 216 2.2.6A: From the Point Model. 216 2.2.6B: Rates Calculated without Point Model assumptions 221 2.3 Gamma pulse height (to be completed) 227 2.4 Active Neutron Example: Cf Shuffler. 231 2.4.1 Description and input file. 231 2.4.2 Results 234 Section 3: Examples of Advanced Concepts 240 Section 3.1 Variance Reduction 240 3.1.1 Introduction 240 DRAFT 6 3.1.2 Multigroup Weight Windows and Time Splitting: Lead Slowing Down Spectrometer 242 3.1.2.1 Input File Notes 253 3.1.2.2 Variance Reduction Step 1: simplify problem and add weight window generator 256 3.1.2.3 Iteration 2 .261 3.1.2.4 Additional iterations 263 3.1.2.5 Cylindrical Mesh Weight Window Summary 267 3.1.3 Cell-based weight windows for the Lead Slowing Down Spectrometer 271 3.1.4 Time splitting 277 3.1.5 Variance Reduction for the Cf Shuffler. 280 3.1.5.1 Cf Shuffler modified input 280 3.1.5.2 Particle production bias, time splitting, and windows 285 3.1.5.3 Analysis of Cf Shuffler Variance Reduction 288 3.2 DXTRAN and Other Capabilities for Distributed Source Problems 288 3.2.1 UF6 Cask Model 290 3.2.2 DXTRAN 300 3.2.3 Source Position Biasing 307 3.2.4 Best Single Detector Solution 310 3.3 Neutron Detector Operation in More Detail. 318 3.3.1 Introduction 318 (i) Make reaction products (model, data) and recoil nuclei 318 (ii) Track created particles in real gas composition 321 (iii) Tally energy deposition of particles in active volume (F8 CAP EDEP for coincidence/multiplicity counting) 322 Examples 322 3He detector Pulse Height. 322 3He Detector Coincidence Calculation 324 10B-lined detectors 325 References 332 Section 4: Additional Topics 332 4.1 Troubleshooting or "How can I be confident in the results?" 332 4.1.1 Geometry and Materials. 333 4.1.2 Detector modelling 334 DRAFT 7 4.1.3 Source modelling 334 4.1.4 Sample modelling 335 4.1.5 Tracking limitations 335 4.1.6 Nuclear Data 335 4.1.7 Statistics 336 4.1.8 User .337 4.1.9 Summary and Conclusions - What to do?. 337 4.2.1 Analysis of Delayed Neutron Production 338 4.2.2 Comparison of Table Physics vs Model Physics 342 5 References and Bibliography. 354 6 Table of Figures 355.
    Additional Edition: ISBN 3-031-04128-3
    Language: English
    Library Location Call Number Volume/Issue/Year Availability
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    FU Berlin
  • 6
    Online Resource
    Online Resource
    Monte Carlo N-particle simulations for nuclear detection and safeguards : an examples-based guide for students and practitioners (2022)
    Cham, Switzerland :Springer,
    Details
    UID:
    kobvindex_HPB1346988713
    Format: 1 online resource (xv, 307 pages) : , illustrations (some color)
    ISBN: 9783031041297 , 3031041291
    Content: This open access book is a pedagogical, examples-based guide to using the Monte Carlo N-Particle (MCNPª) code for nuclear safeguards and non-proliferation applications. The MCNP code, general-purpose software for particle transport simulations, is widely used in the field of nuclear safeguards and non-proliferation for numerous applications including detector design and calibration, and the study of scenarios such as measurement of fresh and spent fuel. This book fills a gap in the existing MCNP software literature by teaching MCNP software usage through detailed examples that were selected based on both student feedback and the real-world experience of the nuclear safeguards group at Los Alamos National Laboratory. MCNP input and output files are explained, and the technical details used in MCNP input file preparation are linked to the MCNP code manual. Benefiting from the authors’ decades of experience in MCNP simulation, this book is essential reading for students, academic researchers, and practitioners whose work in nuclear physics or nuclear engineering is related to non-proliferation or nuclear safeguards. Each chapter comes with downloadable input files for the user to easily reproduce the examples in the text.
    Note: Chapter 1: Introduction -- Chapter 2: Basic Concepts -- Chapter 3: Examples for Nuclear Safeguards Applications -- Chapter 4: Examples of Advanced Concepts -- Chapter 5: Additional Topics.
    Additional Edition: ISBN 3031041283
    Additional Edition: ISBN 9783031041280
    Additional Edition: ISBN 3031041313
    Additional Edition: ISBN 9783031041310
    Language: English
    Keywords: Electronic books.
    DOI: 10.1007/978-3-031-04129-7
    URL: SpringerLink
    URL: Click here to view book
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    HPol Brandenburg
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