Energy Spectrum Characterization of the Reed Research Reactor Neutron Beam PDF Download

Author: Moriah N. Tobin
Publisher:
ISBN:
Category :
Languages : en
Pages : 92

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Author: International Atomic Energy Agency
Publisher: IAEA Tecdoc
ISBN: 9789201089151
Category : Science
Languages : en
Pages : 0

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Annotation This publication aims to expand the knowledge and understanding of material behaviour in terms of their characterization and qualification under extreme conditions for nuclear energy technologies, and also to contribute to the enhancement of utilization and applications of research reactor and accelerator based neutron sources.

Author: C. Z. Serpan
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 230

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Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 764

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Author: David K. Bewley
Publisher: CRC Press
ISBN: 9780852740934
Category : Medical
Languages : en
Pages : 206

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Over fifty years have passed since the first patient was treated with fast neutrons, but this form of therapy is still a matter of bitter dispute. Neutron generators have been installed in many countries and now patients can be treated with equipment that is technically similar to modern megavoltage x-ray equipment. The Physics and Radiobiology of Fast Neutron Beams presents a full discussion of the physical and radiobiological factors governing the production and use of fast neutron beams for therapy. The book discusses vastly improved neutron generators, advances in the standardization of dosimetric methods, and the specification of radiation quality. In addition, it explores nuclear methods of analysis, particularly neutron activation analysis in vivo. Influencing the place of radiotherapy with neutrons and other heavy particles, the radiobiological factors governing the treatment of cancer with radiation are examined. The author also studies the radiation hazard of neutrons, a matter of importance in the use of neutrons for chemical analysis in vivo. The Physics and Radiobiology of Fast Neutron Beams will be a valuable introduction to the subject for radiotherapists, medical physicists, radiographers, and radiobiologists new to the field. The book is also a useful summary of current knowledge for those already established in the use of fast neutrons for medical purposes.

Author: Yonghao Chen
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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The neutron time-of-flight (n_TOF)facility at CERN is a unique worldwide pulsedneutron source to measure the nuclear data over thewidest energy range with two beam lines currentlyexploited. One is horizontal with a ~185 metersflight path, sending neutrons to experimental area-1(EAR-1). The second one is a new line sendingneutrons vertically to experimental area-2 (EAR-2)with a ~20 meters flight path.The first part of this PhD work is dedicated to thecharacterization of the beam (flux, geometricalprofile, energy spectrum) of the new EAR-2 neutronbeam, of the utmost importance for the experimentalproposals and analyses. An experiment was carriedout at EAR-2, based on PPAC detectors looking atfission of 235U, and the beam profile and neutronflux have been obtained for the entire availableenergy range (from thermal to 200 MeV).The second part of the thesis aims to study theneutron-induced fission of 237Np. 237Np isabundantly produced in present nuclear reactor andis one of the major long-lived components ofnuclear waste which can be considered as apotential target of incineration in fast neutronreactors. Consequently its neutron-induced fissioncross section has been measured at differentfacilities. However, significant discrepancies existbetween different experiments. Especially, therecent one performed at n_TOF in 2010 is about 6%higher by comparison to the evaluation data basedon previous experiments. Therefore an experimenthas been performed at n_TOF EAR-1 to measure itsfission cross section, in a configuration allowing anaccurate control of the detection efficiency, aimingto give a definite answer to the puzzle. In this work,we found that the efficiencies for different targetelements are different, even though they havesimilar thickness, reflecting the conditions ofelectrodeposition. After application of thisefficiency correction in the energy range from 1 to 5MeV, the newly extracted fission cross section is 2-3% lower compared with our previous measurementin 2010, however they are 3-4% higher than the.

Author: Joseph M. Harrer
Publisher:
ISBN: 9780870790058
Category : Technology & Engineering
Languages : en
Pages : 1052

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Author: Romel Siqueira França
Publisher:
ISBN:
Category :
Languages : en
Pages : 137

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This research presents the characterization, modeling, and design of the UFTR (University of Florida Training Reactor) radiation beam ports for reactor analysis applications. Extensive validation of beam port is required. Using MCNP5 results were produced for the multigroup neutron flux distributions, neutron spectrum and neutron reaction rates. Due to the strength of the neutron source in the reactor core, the neutron flux distribution and reaction rate can be monitored along the radiation beam port. The goal of the design in this research is to determine the neutron flux distribution, neutron energy flux and neutron reaction rate throughout the beam port. The calculation of the neutron flux distribution, neutron spectrum and neutron reaction rates along the beam port were tallied. To compute the multigroup neutron flux distributions, and neutron energy flux FMESH4 and *F4 tallies were used, respectively. Sets of 47 and 62 energy groups were analyzed for these tallies. To calculate neutron reaction rates, the tally F4 along with the tally multiplier FM4 was used.

Author: Toria E. Ellis
Publisher:
ISBN:
Category :
Languages : en
Pages : 56

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Author: Herbert J. C. Kouts
Publisher:
ISBN:
Category : Neutron beams
Languages : en
Pages : 36

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