Neutron Spectra from Mock Fission Sources

Neutron Spectra from Mock Fission Sources PDF Author: Eugene Tochilin
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 30

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Neutron Spectra from Mock Fission Sources

Neutron Spectra from Mock Fission Sources PDF Author: Eugene Tochilin
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 30

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Preparation of a Mock Fission Neutron Source

Preparation of a Mock Fission Neutron Source PDF Author: Don S. Martin
Publisher:
ISBN:
Category : Neutron sources
Languages : en
Pages : 12

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Photoneutron Sources

Photoneutron Sources PDF Author: B. W. Sargent
Publisher:
ISBN:
Category : Neutron sources
Languages : en
Pages : 8

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Elements of Slow-Neutron Scattering

Elements of Slow-Neutron Scattering PDF Author: J. M. Carpenter
Publisher: Cambridge University Press
ISBN: 0521857813
Category : Science
Languages : en
Pages : 539

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Book Description
This book provides a comprehensive and up-to-date introduction to the fundamental theory and applications of slow-neutron scattering.

Neutron Generators for Analytical Purposes

Neutron Generators for Analytical Purposes PDF Author: International Atomic Energy Agency
Publisher: IAEA Radiation Technology Repo
ISBN: 9789201251107
Category : Science
Languages : en
Pages : 145

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Book Description
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.

Calibration of a Mock Fission Neutron Source by Indium Resonance Mapping of the Standard Graphite Pile

Calibration of a Mock Fission Neutron Source by Indium Resonance Mapping of the Standard Graphite Pile PDF Author: C. J. McDole
Publisher:
ISBN:
Category : Indium
Languages : en
Pages : 32

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Storage and Hybridization of Nuclear Energy

Storage and Hybridization of Nuclear Energy PDF Author: Hitesh Bindra
Publisher: Academic Press
ISBN: 0128139765
Category : Science
Languages : en
Pages : 302

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Book Description
Storage and Hybridization of Nuclear Energy: Techno-economic Integration of Renewable and Nuclear Energy provides a unique analysis of the storage and hybridization of nuclear and renewable energy. Editor Bindra and his team of expert contributors present various global methodologies to obtain the techno-economic feasibility of the integration of storage or hybrid cycles in nuclear power plants. Aimed at those studying, researching and working in the nuclear engineering field, this book offers nuclear reactor technology vendors, nuclear utilities workers and regulatory commissioners a very unique resource on how to access reliable, flexible and clean energy from variable-generation. - Presents a unique view on the technologies and systems available to integrate renewables and nuclear energy - Provides insights into the different methodologies and technologies currently available for the storage of energy - Includes case studies from well-known experts working on specific integration concepts around the world

Managing Global Warming

Managing Global Warming PDF Author: Trevor Letcher
Publisher: Academic Press
ISBN: 0128141050
Category : Business & Economics
Languages : en
Pages : 822

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Book Description
Managing Global Warming: An Interface of Technology and Human Issues discusses the causes of global warming, the options available to solve global warming problems, and how each option can be realistically implemented. It is the first book based on scientific content that presents an overall reference on both global warming and its solutions in one volume. Containing authoritative chapters written by scientists and engineers working in the field, each chapter includes the very latest research and references on the potential impact of wind, solar, hydro, geo-engineering and other energy technologies on climate change. With this wide ranging set of topics and solutions, engineers, professors, leaders and policymakers will find this to be a valuable handbook for their research and work. - Presents chapters that are accompanied by an easy reference summary - Includes up-to-date options and technical solutions for global warming through color imagery - Provides up-to-date information as presented by a collection of renowned global experts

Flux and Spectral Measurements of Primary and Moderated Neutron Sources

Flux and Spectral Measurements of Primary and Moderated Neutron Sources PDF Author: E. Tochilin
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 38

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Book Description
Radioactive (a, n) neutron sources include Ra-Be, PuF4, and four PuBe13 sources. Comparative neutron emission rates were determined by two separate methods: (1) the manganese sulfate bath with appropriate corrections made for fast neutron escape or capture and for thermal neutron capture by the source; and (2) long counter measurements corrected for energy response and so rce anisotropy. Agreement to within 1 percent was obtained by the two independent methods. A Ra-Be source calibrated against the NBS neutron standard was used as a primary reference Spectral measurements of PuBe13 and PuF4 neutron sources were made with nuclear emulsions. By the use of cylindrical plastic and lead absorbers, an effort was made to moderate the PuBe13 spectrum and thereby obtain additional calibration points for instrument response studies. Spectral changes were initially studied with the doublemoderator technique, followed by later measurements with nuclear emulsions. From flux and spectral measurements of the primary and moderated radioactive sources, the first collision tissue dose was calculated and, in turn, compared to experimental measurements of absorbed dose with proportional counters designed according to the Bragg-Gray principle. (Author).

Neutrons from ([alpha], N) Sources

Neutrons from ([alpha], N) Sources PDF Author: Wilmot N. Hess
Publisher:
ISBN:
Category : Alpha rays
Languages : en
Pages : 46

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