Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 46
Book Description
The Monte Carlo code MCNP is used in simulations of neutron well logging in granite to detect water and TCA (C2H3Cl3), a common ground contaminant, in fractures of 1 cm and 1 mm thickness at various distances and orientations. Also simulated is neutron well logging in wet sand to detect TCA and lead (Pb) at various uniform concentrations. The 3H(d, n) (DT) and2H(d, n) (DD) neutron producing reactions are used in the simulations to assess the relative performance of each. Simulations are also performed to determine the efficiency of several detector materials such as CdZnTe, Ge and NaI as a function of photon energy. Results indicate that, by examining the signal from the 6.11 MeV gamma from the thermal neutron capture of Cl in TCA, trace amounts (few ppm) are detectable in saline free media. Water and TCA filled fractures are also detectable. These results are summarized in Tables 7--21. Motivation for this work is based on the need for detection of trace environmental pollutants as well as possible fracture characterization of geologic media.
Monte Carlo Simulations of Neutron Well-logging in Granite and Sand to Detect Water and Trichloroethane (TCA).
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 46
Book Description
The Monte Carlo code MCNP is used in simulations of neutron well logging in granite to detect water and TCA (C2H3Cl3), a common ground contaminant, in fractures of 1 cm and 1 mm thickness at various distances and orientations. Also simulated is neutron well logging in wet sand to detect TCA and lead (Pb) at various uniform concentrations. The 3H(d, n) (DT) and2H(d, n) (DD) neutron producing reactions are used in the simulations to assess the relative performance of each. Simulations are also performed to determine the efficiency of several detector materials such as CdZnTe, Ge and NaI as a function of photon energy. Results indicate that, by examining the signal from the 6.11 MeV gamma from the thermal neutron capture of Cl in TCA, trace amounts (few ppm) are detectable in saline free media. Water and TCA filled fractures are also detectable. These results are summarized in Tables 7--21. Motivation for this work is based on the need for detection of trace environmental pollutants as well as possible fracture characterization of geologic media.
Publisher:
ISBN:
Category :
Languages : en
Pages : 46
Book Description
The Monte Carlo code MCNP is used in simulations of neutron well logging in granite to detect water and TCA (C2H3Cl3), a common ground contaminant, in fractures of 1 cm and 1 mm thickness at various distances and orientations. Also simulated is neutron well logging in wet sand to detect TCA and lead (Pb) at various uniform concentrations. The 3H(d, n) (DT) and2H(d, n) (DD) neutron producing reactions are used in the simulations to assess the relative performance of each. Simulations are also performed to determine the efficiency of several detector materials such as CdZnTe, Ge and NaI as a function of photon energy. Results indicate that, by examining the signal from the 6.11 MeV gamma from the thermal neutron capture of Cl in TCA, trace amounts (few ppm) are detectable in saline free media. Water and TCA filled fractures are also detectable. These results are summarized in Tables 7--21. Motivation for this work is based on the need for detection of trace environmental pollutants as well as possible fracture characterization of geologic media.
A Monte Carlo Computation Being Made for Neutron Attenuation in Water
Author: M. Lewis Nelson
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 16
Book Description
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 16
Book Description
Monte Carlo Simulation of Duel-spaced Neutron Porosity Well-logging Tool Responses
Author: Medhat Wahba Mickael
Publisher:
ISBN:
Category :
Languages : en
Pages : 206
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 206
Book Description
Monte Carlo Methods and Their Application to Neutron Transport Problems
Author: Jerome Spanier
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 72
Book Description
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 72
Book Description
Monte Carlo Principles and Neutron Transport Problems
Author: Jerome Spanier
Publisher: Courier Corporation
ISBN: 0486462935
Category : Mathematics
Languages : en
Pages : 258
Book Description
This two-part treatment introduces the general principles of the Monte Carlo method within a unified mathematical point of view, applying them to problems in neutron transport. It describes several efficiency-enhancing approaches, including the method of superposition and simulation of the adjoint equation based on reciprocity. The first half of the book presents an exposition of the fundamentals of Monte Carlo methods, examining discrete and continuous random walk processes and standard variance reduction techniques. The second half of the text focuses directly on the methods of superposition and reciprocity, illustrating their applications to specific neutron transport problems. Topics include the computation of thermal neutron fluxes and the superposition principle in resonance escape computations.
Publisher: Courier Corporation
ISBN: 0486462935
Category : Mathematics
Languages : en
Pages : 258
Book Description
This two-part treatment introduces the general principles of the Monte Carlo method within a unified mathematical point of view, applying them to problems in neutron transport. It describes several efficiency-enhancing approaches, including the method of superposition and simulation of the adjoint equation based on reciprocity. The first half of the book presents an exposition of the fundamentals of Monte Carlo methods, examining discrete and continuous random walk processes and standard variance reduction techniques. The second half of the text focuses directly on the methods of superposition and reciprocity, illustrating their applications to specific neutron transport problems. Topics include the computation of thermal neutron fluxes and the superposition principle in resonance escape computations.
Monte Carlo Method
A Monte Carlo Code for the Transport of Neutrons
Author: William V. Baxter
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 40
Book Description
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 40
Book Description
Monte Carlo N-Particle Simulations for Nuclear Detection and Safeguards
Author: John S. Hendricks
Publisher: Springer Nature
ISBN: 3031041291
Category : Science
Languages : en
Pages : 316
Book Description
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.
Publisher: Springer Nature
ISBN: 3031041291
Category : Science
Languages : en
Pages : 316
Book Description
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.
Monte Carlo Methods for Equilibrium Solutions in Neutron Multiplication
Author: E. L. Kaplan
Publisher:
ISBN:
Category : Equilibrium
Languages : en
Pages : 114
Book Description
Publisher:
ISBN:
Category : Equilibrium
Languages : en
Pages : 114
Book Description
Monte Carlo Particle Transport Methods
Author: I. Lux
Publisher: CRC Press
ISBN: 1351083287
Category : Science
Languages : en
Pages : 530
Book Description
With this book we try to reach several more-or-less unattainable goals namely: To compromise in a single book all the most important achievements of Monte Carlo calculations for solving neutron and photon transport problems. To present a book which discusses the same topics in the three levels known from the literature and gives us useful information for both beginners and experienced readers. It lists both well-established old techniques and also newest findings.
Publisher: CRC Press
ISBN: 1351083287
Category : Science
Languages : en
Pages : 530
Book Description
With this book we try to reach several more-or-less unattainable goals namely: To compromise in a single book all the most important achievements of Monte Carlo calculations for solving neutron and photon transport problems. To present a book which discusses the same topics in the three levels known from the literature and gives us useful information for both beginners and experienced readers. It lists both well-established old techniques and also newest findings.