Download or read book An Evaluation of Monte Carlo Simulations of Neutron Multiplicity Measurements of Plutonium Metal written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monte Carlo Simulations of Multiplicity Measurements of the Plutonium BeRP Ball written by and published by . This book was released on 2009 with total page 21 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monte Carlo Evaluation of Passive NMIS for Assay of Plutonium in Shielded Containers written by and published by . This book was released on 2000 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: Preliminary Monte Carlo simulations have demonstrated that passive Nuclear Materials Identification System (NMIS) measurements can be used to determine the mass of Pu in AT400-R containers with measurement times as short as a few minutes. The sensitivity of the proposed detectors to gamma rays should enhance this measurement method because the gamma rays from fission, induced or spontaneous, escape this container more easily than neutrons. In these calculations, the container contained two Pu spheres with mass varying between 0.5 and 2 Kg with (approximately)6 wt% {sup 240 }Pu.
Download or read book Monte Carlo N Particle Simulations for Nuclear Detection and Safeguards written by John S. Hendricks and published by Springer Nature. This book was released on 2022-09-27 with total page 316 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book Monte Carlo Evaluation of the Improvements in Nuclear Materials Identification System NMIS Resulting From a DT Neutron Generator written by and published by . This book was released on 2002 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear safeguards active measurements that rely on the time correlation between fast neutrons and gamma rays from the same fission are a promising technique. Previous studies have shown the feasibility of this method, in conjunction with the use of artificial neural networks, to estimate the mass and enrichment of fissile samples enclosed in special, sealed containers. This paper evaluates the use of the associated particle sealed tube neutron generator (APSTNG) as the interrogation source in correlation measurements. The results show that its use is of particular importance when floor reflections are present. The Nuclear Materials Identification System (NMIS) presently uses 252Cf ionization chambers as interrogation sources for the time-dependent coincidence measurements. Because triggers from this source are associated with neutrons emitted in any direction, adjacent materials such as the floor and nearby containers could affect the measurements and should be accounted for. Conversely, the APSTNG, together with an alpha particle detector, defines a cone of neutrons that can be aimed at the item under verification, thus removing the effects of nearby materials from the time-dependent coincidence distributions. Monte Carlo calculations were performed using MCNP-POLIMI, a modified version of the standard MCNP code. The code attempts to calculate more correctly quantities that depend on the second moment of the neutron and gamma distributions. The simulations quantified the sensitivity enhancements and removal of the effects of nearby materials by substituting the traditional 252Cf source with the APSTNG.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 922 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monte Carlo Principles and Neutron Transport Problems written by Jerome Spanier and published by Courier Corporation. This book was released on 2008-01-01 with total page 258 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Download or read book A Monte Carlo Study of Homogeneous Plutonium and Uranium Mixtures written by Leland Lavele Carter and published by . This book was released on 1964 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Monte Carlo Simulation in the Radiological Sciences written by Richard L. Morin and published by CRC Press. This book was released on 2019-06-04 with total page 244 pages. Available in PDF, EPUB and Kindle. Book excerpt: First Published in 1988, this book offers a full exploration into the applications of the Monte Carlo Simulation. Carefully compiled and filled with a vast repertoire of notes, diagrams, and references this book serves as a useful reference for Students of Radiology, and other practitioners in their respective fields.
Download or read book Advanced Monte Carlo for Radiation Physics Particle Transport Simulation and Applications written by Andreas Kling and published by Springer. This book was released on 2001-10-02 with total page 1224 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book focuses on the state of the art of Monte Carlo methods in radiation physics and particle transport simulation and applications. Special attention is paid to algorithm development for modeling, and the analysis of experiments and measurements in a variety of fields.
Download or read book Monte Carlo Simulation Research on the Spontaneous Fission Yield of 240Pu written by Tianyou Xie and published by . This book was released on 2015 with total page 103 pages. Available in PDF, EPUB and Kindle. Book excerpt: This research describes results of mathematical simulations to predict the spontaneous fission yield of 240Pu thereby guiding selection of a suitable fission product for use as a radiochronometer for weapons grade plutonium. The PUREX process is effective in separating plutonium and uranium in irradiated nuclear fuel from fission products, which may make it possible to use one or more of the spontaneous fission products from 240Pu as a radiochronometer. However, the fission product inventory from the spontaneous fission of 240Pu reported in the literature is quite variable. The non-uniform induced fission probability at multiple neutron energies makes the induced fission yield too complex to be listed as a single value. The neutron flux distribution from a source containing 240Pu is a combination of both spontaneous and induced fissions. Fission products generated in this source are due to a combination of spontaneous and induced fission processes, each with a unique neutron energy distribution and fission product yield. The physical conditions of the source (i.e., size, shape, etc.) will have a significant influence on the neutron flux distribution and the induced fission probability associated with 240Pu. Thus, it is likely that there is a relationship between the combined (spontaneous and induced) fission yield and the physical conditions of the source. Exploring this relationship, a table of values will be generated to predict the combined fission product yield for any source geometry containing 240Pu. Minimizing variations in the source geometry should stabilize the combined fission product yield and provide a means to determine the spontaneous fission probability for 240Pu. This research has identified that the combined fission product yields from 97Zr and 138Xe exhibit less sensitivity to the physical source parameters than other fission products making them good candidates as radiochronometers for age dating weapons-grade plutonium.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975-04 with total page 1082 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Passive Nondestructive Assay of Nuclear Materials written by Doug Reilly and published by . This book was released on 1991 with total page 700 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Active neutron multiplicity and Monte Carlo calculations written by Yannick Pierre Bercy and published by . This book was released on 2001 with total page 170 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book New Monte Carlo Simulations of the LLNL Pulsed sphere Experiments written by and published by . This book was released on 1998 with total page 119 pages. Available in PDF, EPUB and Kindle. Book excerpt: From the late 1960s to about 1985, the Pulsed-Sphere Program at Lawrence Livermore National Laboratory (LLNL) was carried out to measure 14-MeV neutron leakage spectra from target spheres made out of various elements, compounds, and mixtures Data from these experiments have been and continue to be fundamental in the evaluation of neutron Monte Carlo transport codes and cross section data libraries In addition, the data provide important integral information for stockpile stewardship, fusion technology, neutron therapy, and other applications Therefore, comparisons between computer Monte Carlo simulations and the results of these experiments are pivotal for the integral testing of processed nuclear data libraries and transport codes Fortunately, a large subset of data from the pulsed-sphere program (some 70 experiments) is available as a computer file called disp93in Furthermore, in the past few years, there has been a remarkable improvement in computer performance that allows for more realistic simulations by Monte Carlo codes such as TART 4 Previous TART simulations of the pulsed-sphere experiments were performed using simplified models with relatively small numbers of histories and very large solid angle detectors to offset the limitations in computer power. Also, not all the TART input files were created with the same level of detail For example, some input files included the air around the sphere while others did not These factors prompted a study to simulate in more detail all of the available pulsed-sphere experiments using the Monte Carlo transport code, TART, and the LLNL evaluated neutron data library, ENDL The timing of this study is significant because many years have passed since those experiments were done, and only a few people who participated in them are still working at LLNL Their help has been essential for an accurate documentation of the experiments For the Stewardship Program it is important to preserve and make use of as much of the data as possible, because it represents a unique resource and an enormous effort that would be very costly to reproduce The initial part of this study consisted of an analysis of the experimental setup and neutron source characteristics necessary to create the foundation for a TART input file The next task was to create the input files for the various experiments by incorporating particular settings, such as flight path, sphere materials and dimension, etc, to the basic TART input The results of the TART simulations of these experiments will be used to help assess the quality of evaluated data currently in ENDL Further, other nuclear libraries, e g, ENDF/B-VI, JENDL-3, and JEF-2, will be used in the Monte Carlo simulations after being reformatted for TART and other Laboratory codes Finally, this work will be part of the integral check of the new evaluations being prepared for the Stewardship Barn Book by the LLNL Nuclear Data Group.
Download or read book Monte Carlo Simulation of the Upgraded Neutron Gamma Logging Tool SO 5 90 SN Type written by Teresa Cywicka-Jakiel and published by . This book was released on 2005 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book NBS Special Publication written by and published by . This book was released on 1968 with total page 684 pages. Available in PDF, EPUB and Kindle. Book excerpt:
