Higher-Mode Applications of Fission Matrix Capability for MCNP.

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Download or read book Higher-Mode Applications of Fission Matrix Capability for MCNP. written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Fission Matrix Capability for MCNP Monte Carlo

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Book Synopsis Fission Matrix Capability for MCNP Monte Carlo by :

Download or read book Fission Matrix Capability for MCNP Monte Carlo written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In a Monte Carlo criticality calculation, before the tallying of quantities can begin, a converged fission source (the fundamental eigenvector of the fission kernel) is required. Tallies of interest may include powers, absorption rates, leakage rates, or the multiplication factor (the fundamental eigenvalue of the fission kernel, k{sub eff}). Just as in the power iteration method of linear algebra, if the dominance ratio (the ratio of the first and zeroth eigenvalues) is high, many iterations of neutron history simulations are required to isolate the fundamental mode of the problem. Optically large systems have large dominance ratios, and systems containing poor neutron communication between regions are also slow to converge. The fission matrix method, implemented into MCNP[1], addresses these problems. When Monte Carlo random walk from a source is executed, the fission kernel is stochastically applied to the source. Random numbers are used for: distances to collision, reaction types, scattering physics, fission reactions, etc. This method is used because the fission kernel is a complex, 7-dimensional operator that is not explicitly known. Deterministic methods use approximations/discretization in energy, space, and direction to the kernel. Consequently, they are faster. Monte Carlo directly simulates the physics, which necessitates the use of random sampling. Because of this statistical noise, common convergence acceleration methods used in deterministic methods do not work. In the fission matrix method, we are using the random walk information not only to build the next-iteration fission source, but also a spatially-averaged fission kernel. Just like in deterministic methods, this involves approximation and discretization. The approximation is the tallying of the spatially-discretized fission kernel with an incorrect fission source. We address this by making the spatial mesh fine enough that this error is negligible. As a consequence of discretization we get a spatially low-order kernel, the fundamental eigenvector of which should converge faster than that of continuous kernel. We can then redistribute the fission bank to match the fundamental fission matrix eigenvector, effectively eliminating all higher modes. For all computations here biasing is not used, with the intention of comparing the unaltered, conventional Monte Carlo process with the fission matrix results. The source convergence of standard Monte Carlo criticality calculations are, to some extent, always subject to the characteristics of the problem. This method seeks to partially eliminate this problem-dependence by directly calculating the spatial coupling. The primary cost of this, which has prevented widespread use since its inception [2,3,4], is the extra storage required. To account for the coupling of all N spatial regions to every other region requires storing N2 values. For realistic problems, where a fine resolution is required for the suppression of discretization error, the storage becomes inordinate. Two factors lead to a renewed interest here: the larger memory available on modern computers and the development of a better storage scheme based on physical intuition. When the distance between source and fission events is short compared with the size of the entire system, saving memory by accounting for only local coupling introduces little extra error. We can gain other information from directly tallying the fission kernel: higher eigenmodes and eigenvalues. Conventional Monte Carlo cannot calculate this data - here we have a way to get new information for multiplying systems. In Ref. [5], higher mode eigenfunctions are analyzed for a three-region 1-dimensional problem and 2-dimensional homogenous problem. We analyze higher modes for more realistic problems. There is also the question of practical use of this information; here we examine a way of using eigenmode information to address the negative confidence interval bias due to inter-cycle correl ...

Monte Carlo Methods for Equilibrium Solutions in Neutron Multiplication

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ISBN 13 :
Total Pages : 114 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Monte Carlo Methods for Equilibrium Solutions in Neutron Multiplication by : E. L. Kaplan

Download or read book Monte Carlo Methods for Equilibrium Solutions in Neutron Multiplication written by E. L. Kaplan and published by . This book was released on 1958 with total page 114 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Fluka

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ISBN 13 :
Total Pages : 410 pages
Book Rating : 4.X/5 (4 download)

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Book Synopsis Fluka by : Alfredo Ferrari

Download or read book Fluka written by Alfredo Ferrari and published by . This book was released on 2005 with total page 410 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Reactor Criticality and Non-negative Matrices

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ISBN 13 :
Total Pages : 104 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Reactor Criticality and Non-negative Matrices by : Garrett Birkhoff

Download or read book Reactor Criticality and Non-negative Matrices written by Garrett Birkhoff and published by . This book was released on 1957 with total page 104 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Nuclear Reactor Theory

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ISBN 13 :
Total Pages : 648 pages
Book Rating : 4.3/5 (97 download)

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Book Synopsis Nuclear Reactor Theory by : George I. Bell

Download or read book Nuclear Reactor Theory written by George I. Bell and published by . This book was released on 1970 with total page 648 pages. Available in PDF, EPUB and Kindle. Book excerpt: In a part of North Africa where, within miles, the backdrop can change dramatically from snow-blasted mountains to wind-scoured dunes live the Berber people of the Atlas Mountains. In the third book of her trilogy on African women, world-renowned photojournalist Margaret Courtney-Clarke examines the difficult lives and remarkable arts of Berber women. As modern times and modern warfare in Algeria, Morocco, and Tunisia have encroached on their centuries-old traditions, Berber women have begun to give up the old ways. Imazighen: The Vanishing Traditions of Berber Women is a record of a quickly disappearing way of life. As in her earlier books, Ndebele: The Art of an African Tribe and African Canvas: The Art of West African Women, Courtney-Clarke succeeds in capturing the spirit of the women by experiencing their world from season to season and by respecting their values and traditions. Through photographs, interviews, and observations, Courtney-Clarke documents the Berber women as they stoically carry water and firewood on their backs for miles of rocky terrain. And she records the beauty they have magically produced in their lives - through their spinning and weaving and their carefully coiled pottery - a metaphor for survival and creativity. Geraldine Brooks, award-winning journalist and an expert on life in the Middle East, accompanied Courtney-Clarke on her last trip to North Africa, and has written moving, thoughtful essays on the struggle of existence among the Berbers. With a glossary of Berber terms and a detailed map of the region, this book is not only a handsomely illustrated volume of the triumph of the arts of the Berber women, but a dramatic record of a people yielding to the pressures of the twentieth century.

Safeguards Techniques and Equipment

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ISBN 13 : 9789201189103
Total Pages : 146 pages
Book Rating : 4.1/5 (891 download)

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Book Synopsis Safeguards Techniques and Equipment by : International Atomic Energy Agency

Download or read book Safeguards Techniques and Equipment written by International Atomic Energy Agency and published by . This book was released on 2011 with total page 146 pages. Available in PDF, EPUB and Kindle. Book excerpt: The 1990s saw significant developments in the global non-proliferation landscape, resulting in a new period of safeguards development. The current publication, which is the second revision and update of IAEA/NVS/1, is intended to give a full and balanced description of the safeguards techniques and equipment used for nuclear material accountancy, containment and surveillance measures, environmental sampling, and data security. New features include a section on new and novel technologies. As new verification measures continue to be developed, the material in this book will be reviewed periodically and updated versions issued.

Accelerator-Driven System at Kyoto University Critical Assembly

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Publisher : Springer
ISBN 13 : 9789811603433
Total Pages : 352 pages
Book Rating : 4.6/5 (34 download)

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Book Synopsis Accelerator-Driven System at Kyoto University Critical Assembly by : Cheol Ho Pyeon

Download or read book Accelerator-Driven System at Kyoto University Critical Assembly written by Cheol Ho Pyeon and published by Springer. This book was released on 2021-03-20 with total page 352 pages. Available in PDF, EPUB and Kindle. Book excerpt: This open access book is a unique compilation of experimental benchmark analyses of the accelerator-driven system (ADS) at the Kyoto University Critical Assembly (KUCA) on the most recent advances in the development of computational methods. It is devoted especially to nuclear engineers and scientists. Readers will find a detailed description of advanced measurement techniques and calculation methodologies for the ADS with 14 MeV neutrons and high-energy neutrons (with combined use of 100 MeV protons and Pb-Bi target) at KUCA. Additionally, experimental results of nuclear transmutation of minor actinides by ADS and at a critical state are included. Readers also have access to benchmarks of specific ADS experiments with raw data in the Appendix. The book is a valuable resource for the ADS experiments at KUCA which are globally recognized as both static and kinetic studies from the point of view of fundamental research.

Neutron Generators for Analytical Purposes

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Publisher : IAEA Radiation Technology Repo
ISBN 13 : 9789201251107
Total Pages : 145 pages
Book Rating : 4.2/5 (511 download)

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Book Synopsis Neutron Generators for Analytical Purposes by : International Atomic Energy Agency

Download or read book Neutron Generators for Analytical Purposes written by International Atomic Energy Agency and published by IAEA Radiation Technology Repo. This book was released on 2012 with total page 145 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication addresses recent developments in neutron generator (NG) technology. It presents information on compact instruments with high neutron yield to be used for neutron activation analysis (NAA) and prompt gamma neutron activation analysis in combination with high count rate spectrometers. Traditional NGs have been shown to be effective for applications including borehole logging, homeland security, nuclear medicine and the on-line analysis of aluminium, coal and cement. Pulsed fast thermal neutron analysis, as well as tagged and timed neutron analysis, are additional techniques which can be applied using NG. Furthermore, NG can effectively be used for elemental analysis and is also effective for analysis of hidden materials by neutron radiography. Useful guidelines for developing NG based research laboratories are also provided in this publication.

Strategy and Methodology for Radioactive Waste Characterization

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Publisher : IAEA
ISBN 13 :
Total Pages : 188 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Strategy and Methodology for Radioactive Waste Characterization by : International Atomic Energy Agency

Download or read book Strategy and Methodology for Radioactive Waste Characterization written by International Atomic Energy Agency and published by IAEA. This book was released on 2007 with total page 188 pages. Available in PDF, EPUB and Kindle. Book excerpt: Over the past decade significant progress has been achieved in the development of waste characterization and control procedures and equipment as a direct response to ever-increasing requirements for quality and reliability of information on waste characteristics. Failure in control procedures at any step can have important, adverse consequences and may result in producing waste packages which are not compliant with the waste acceptance criteria for disposal, thereby adversely impacting the repository. The information and guidance included in this publication corresponds to recent achievements and reflects the optimum approaches, thereby reducing the potential for error and enhancing the quality of the end product. -- Publisher's description.

Advances in High Temperature Gas Cooled Reactor Fuel Technology

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ISBN 13 : 9789201253101
Total Pages : 639 pages
Book Rating : 4.2/5 (531 download)

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Book Synopsis Advances in High Temperature Gas Cooled Reactor Fuel Technology by : International Atomic Energy Agency

Download or read book Advances in High Temperature Gas Cooled Reactor Fuel Technology written by International Atomic Energy Agency and published by . This book was released on 2012-06 with total page 639 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

Monte Carlo Methods for Particle Transport

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Publisher : CRC Press
ISBN 13 : 042958220X
Total Pages : 214 pages
Book Rating : 4.4/5 (295 download)

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Book Synopsis Monte Carlo Methods for Particle Transport by : Alireza Haghighat

Download or read book Monte Carlo Methods for Particle Transport written by Alireza Haghighat and published by CRC Press. This book was released on 2020-08-09 with total page 214 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fully updated with the latest developments in the eigenvalue Monte Carlo calculations and automatic variance reduction techniques and containing an entirely new chapter on fission matrix and alternative hybrid techniques. This second edition explores the uses of the Monte Carlo method for real-world applications, explaining its concepts and limitations. Featuring illustrative examples, mathematical derivations, computer algorithms, and homework problems, it is an ideal textbook and practical guide for nuclear engineers and scientists looking into the applications of the Monte Carlo method, in addition to students in physics and engineering, and those engaged in the advancement of the Monte Carlo methods. Describes general and particle-transport-specific automated variance reduction techniques Presents Monte Carlo particle transport eigenvalue issues and methodologies to address these issues Presents detailed derivation of existing and advanced formulations and algorithms with real-world examples from the author’s research activities

Magnetic Fusion Technology

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Publisher : Springer Science & Business Media
ISBN 13 : 1447155564
Total Pages : 816 pages
Book Rating : 4.4/5 (471 download)

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Book Synopsis Magnetic Fusion Technology by : Thomas J. Dolan

Download or read book Magnetic Fusion Technology written by Thomas J. Dolan and published by Springer Science & Business Media. This book was released on 2014-02-10 with total page 816 pages. Available in PDF, EPUB and Kindle. Book excerpt: Magnetic Fusion Technology describes the technologies that are required for successful development of nuclear fusion power plants using strong magnetic fields. These technologies include: • magnet systems, • plasma heating systems, • control systems, • energy conversion systems, • advanced materials development, • vacuum systems, • cryogenic systems, • plasma diagnostics, • safety systems, and • power plant design studies. Magnetic Fusion Technology will be useful to students and to specialists working in energy research.

Energy Research Abstracts

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ISBN 13 :
Total Pages : 926 pages
Book Rating : 4.3/5 (243 download)

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Book Synopsis Energy Research Abstracts by :

Download or read book Energy Research Abstracts written by and published by . This book was released on 1980 with total page 926 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor

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Publisher : IOS Press
ISBN 13 : 9781586036966
Total Pages : 160 pages
Book Rating : 4.0/5 (369 download)

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Book Synopsis Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor by : Willem Frederik Geert van Rooijen

Download or read book Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor written by Willem Frederik Geert van Rooijen and published by IOS Press. This book was released on 2006 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.

Handbook of Nuclear Engineering

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Publisher : Springer Science & Business Media
ISBN 13 : 0387981306
Total Pages : 3701 pages
Book Rating : 4.3/5 (879 download)

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Book Synopsis Handbook of Nuclear Engineering by : Dan Gabriel Cacuci

Download or read book Handbook of Nuclear Engineering written by Dan Gabriel Cacuci and published by Springer Science & Business Media. This book was released on 2010-09-14 with total page 3701 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.

Database of Prompt Gamma Rays from Slow Neutron Capture for Elemental Analysis

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Publisher : IAEA
ISBN 13 :
Total Pages : 282 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Database of Prompt Gamma Rays from Slow Neutron Capture for Elemental Analysis by : International Atomic Energy Agency

Download or read book Database of Prompt Gamma Rays from Slow Neutron Capture for Elemental Analysis written by International Atomic Energy Agency and published by IAEA. This book was released on 2007 with total page 282 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron-capture prompt-gamma activation analysis (PGAA) is particularly valuable as a non-destructive nuclear method in the measurement of elements that do not form neutron capture products with delayed gamma ray emissions. Inaccurate and incomplete data have been a significant hindrance in the qualitative and quantitative analysis of complicated capture gamma spectra by means of PGAA. This database was produced to improve the quality and quantity of required data in order to make possible the reliable application of PGAA in fields such as materials science, geology, mining, archaeology, environment, food analysis and medicine. The database provides a variety of tables for all natural elements (from H to U) including the following data: isotopic composition, thermal radiative cross-section (total and partial), Westcott g-factors, energy of the gamma rays (prompt and delayed), decay mode, half-life and branching ratios. The CD-ROM included in this publication contains the database, the retrieval system and important electronic documents related to the project.--Publisher's description.