Thermal Neutron Source Study PDF Download

Author: Atomic Energy of Canada Limited
Publisher: Chalk River, Ont. : Chalk River Nuclear Laboratories
ISBN:
Category : Neutron sources
Languages : en
Pages : 25

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Author: Kueh Chin Yap
Publisher:
ISBN:
Category : Neutron radiography
Languages : en
Pages : 113

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Book Description

Author: Albert Wattenberg
Publisher:
ISBN:
Category : Neutron sources
Languages : en
Pages : 42

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Book Description

Author: Jan Philipp Dabruck
Publisher: Springer
ISBN: 3030056392
Category : Science
Languages : en
Pages : 200

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Book Description
In the present work, the target station of the accelerator-driven neutron source HBS is optimized in comprehensive parameter studies using the Monto-Carlo method. The dependence of the most important performance characteristics of such a system on the external parameters is investigated neglecting technical and mechanical limitations. In this way, qualitative and quantitative statements for all possible configurations and envisaged applications can be derived and should be considered in the detailed planning of such facilities. For this purpose, different scenarios are considered that place completely different requirements on the design of the target station. The central statements derived in this thesis can be transferred to any framework conditions, such as different accelerator energies, so that these results can be used in the development of other neutron sources, which together with the HBS form a European network and provide a prosperous community in neutron science.

Author: National Research Council
Publisher: National Academies Press
ISBN: 0309075599
Category : Science
Languages : en
Pages : 211

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Book Description
The Committee on Dosimetry for the Radiation Effects Research Foundation (RERF) was set up more than a decade ago at the request of the U.S. Department of Energy. It was charged with monitoring work and experimental results related to the Dosimetry System 1986 (DS86) used by RERF to reconstruct the radiation doses to the survivors in Hiroshima and Nagasaki. At the time it was established, DS86 was believed to be the best available dosimetric system for RERF, but questions have persisted about some features, especially the estimates of neutrons resulting from the Hiroshima bomb. This book describes the current situation, the gamma-ray dosimetry, and such dosimetry issues as thermal-neutron discrepancies between measurement and calculation at various distances in Hiroshima and Nagasaki. It recommends approaches to bring those issues to closure and sets the stage for the recently convened U.S. and Japan Working Groups that will develop a new dosimetry for RERF. The book outlines the changes relating to DS86 in the past 15 years, such as improved numbers that go into, and are part of, more sophisticated calculations for determining the radiations from bombs that reach certain distances in air, and encourages incorporation of the changes into a revised dosimetry system.

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.

Author: J. M. Carpenter
Publisher: Cambridge University Press
ISBN: 0521857813
Category : Science
Languages : en
Pages : 539

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

Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
Parameter studies, design calculations and initial neutronic performance measurements have been completed for a new thermal neutron beamline to be used for neutron capture therapy cell and small-animal radiobiology studies at the University of Missouri Research Reactor. The beamline features the use of single-crystal silicon and bismuth sections for neutron filtering and for reduction of incident gamma radiation. The calculated and measured thermal neutron flux produced at the irradiation location is on the order of 9.5x108 neutrons/cm2-s, with a measured cadmium ratio (Au foils) of 105, indicating a well-thermalized spectrum.

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).

Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
Parameter studies, design calculations and initial neutronic performance measurements have been completed for a new thermal neutron beamline to be used for neutron capture therapy cell and small-animal radiobiology studies at the University of Missouri Research Reactor. The beamline features the use of single-crystal silicon and bismuth sections for neutron filtering and for reduction of incident gamma radiation. The computational models used for the final beam design and performance evaluation are based on coupled discrete-ordinates and Monte Carlo techniques that permit detailed modeling of the neutron transmission properties of the filtering crystals with very few approximations. This is essential for detailed dosimetric studies required for the anticipated research program.