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Activation Cross Sections And Isomeric Cross Section Ratios In Neutron Induced Reactions On Cr Fe And Ni Isotopes In The Energy Range 9 To 21 Mev
Download Activation Cross Sections And Isomeric Cross Section Ratios In Neutron Induced Reactions On Cr Fe And Ni Isotopes In The Energy Range 9 To 21 Mev full books in PDF, epub, and Kindle. Read online Activation Cross Sections And Isomeric Cross Section Ratios In Neutron Induced Reactions On Cr Fe And Ni Isotopes In The Energy Range 9 To 21 Mev ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Activation Cross Sections and Isomeric Cross Section Ratios in Neutron Induced Reactions on Cr-, Fe- and Ni-Isotopes in the Energy Range 9 to 21 MeV by : Andreas Fessler
Download or read book Activation Cross Sections and Isomeric Cross Section Ratios in Neutron Induced Reactions on Cr-, Fe- and Ni-Isotopes in the Energy Range 9 to 21 MeV written by Andreas Fessler and published by . This book was released on 1998 with total page 146 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1967 with total page 1122 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1979 with total page 1180 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Calculated Neutron Induced Reaction Cross Sections from 1 to 20 MeV for All Stable Isotopes of Cr, Fe and Ni by : M. Avrigeanu
Download or read book Calculated Neutron Induced Reaction Cross Sections from 1 to 20 MeV for All Stable Isotopes of Cr, Fe and Ni written by M. Avrigeanu and published by . This book was released on 1989 with total page 66 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Capture Cross-sections for Fast Neutrons by :
Download or read book Capture Cross-sections for Fast Neutrons written by and published by . This book was released on 1948 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Isomeric Cross Section Ratios for Ni58(n, P) Co 58ʹ58 Reaction Induced by Neutrons in the 13.2-15.5 MeV Energy Range by : Sławomir Chojnacki
Download or read book Isomeric Cross Section Ratios for Ni58(n, P) Co 58ʹ58 Reaction Induced by Neutrons in the 13.2-15.5 MeV Energy Range written by Sławomir Chojnacki and published by . This book was released on 1965 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutron Cross Sections by : Victoria McLane
Download or read book Neutron Cross Sections written by Victoria McLane and published by Elsevier. This book was released on 2012-12-02 with total page 850 pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron Cross Sections, Volume 2: Neutron Cross Section Curves presents data for total reaction cross sections and related fission parameters as a function of incident-neutron energy. This book covers energy range from 0.01 eV to 200 MeV to exclude crystalline and magnetic effects for slow neutrons and relativistic effects for high energy neutrons. The data in this volume are grouped into sections corresponding to the element of the target nucleus in the neutron-induced reaction. These sections are ordered in increasing atomic number. Within a section, graphical data are presented for the natural element followed by the isotopes of that element in order of increasing atomic mass. A list of the reaction types is provided at the end of each section. This book also provides graphical section, wherein each graphical page is annotated on the outer edge with a symbol for an element or isotope followed by the list of the cross section data for that element or isotope. The data plotted in the graphical section are tagged by a mnemonic consisting of year, laboratory, and author's last name. This tag can be used to find the corresponding reference on the bibliographic pages.
Download or read book Physics Briefs written by and published by . This book was released on 1990 with total page 816 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Neutron Activation Cross Sections for Safety of Nuclear Power Plants by : European Communities
Download or read book Neutron Activation Cross Sections for Safety of Nuclear Power Plants written by European Communities and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Results of new activation cross section measurements are presented for the following neutron-induced reactions: 58Ni(n,p)58m+gCo, 58Ni(n,p)58mCo, 58Ni(n,x)57Co, 58Ni(n,2n)57Ni, 60Ni(n,p )60m+gCo, 60Ni(n,p)60mCo, 61Ni(n,p)61Co, 61Ni(n,x)60mCo, 62Ni(n,x)61Co, 59Co(n,2)58m+gCo, 63Cu(n ,a)60m+gCo, 90Zr(n,a)87mSr, 90Zr(n,p)90mY, 91Zr(n,x)90mY, 91Zr(n,p)91mY, 92Zr(n,x)91mY, 92Zr(n,p)92Y, 204Pb(h,n')204Pb, 204(n,2n)203m1+m2Pb, and 207Pb(n,p)207 TI with emphasis on incident energies between 14 and 20 MeV. ln addition, new results have been obtained for the isomeric cross section ratios of the 58Ni(n,p )58m,gCo, the 60Ni(n ,p )60m,gCo and 59Co(n,2n)58m,gCo reactions. The irradiations were carried out at the 7 MV Van de Graaff accelerator at IRMM, Geel. Quasi mono-energetic neutrons with energies between 13.3 and 20,5 MeV were produced via the 3H(d,n)4He reaction, and for the production of neutrons with energies between 1 and 3.4 MeV the 3H(p,n)3He reaction was used. In some cases isotopically enriched materials were used to enhance the reaction yield or to facilitate correction for interfering reactions leading to the same product. The half lives for the reaction products range from 6.3 s to 5.3 years. A pneumatic sample transport system was used for the measurements of short-lived reaction cross sections. All reaction cross sections measured in the present work are referenced to the 27Al(n,a)24Na standard reaction cross section. The neutron flux spectra were determined using neutron-spectrum information obtained by the time-of-flight method and the spectral index method that involves 115In(n,n')115mIn, 58Ni(n,p)58m+gCo, 27Al(n,p)27Mg, 56Fe(n,p)56Mn, 27Al(n,a)24Na and 93 Nb(n,2n)92mNb monitor reactions with distinct energy thresholds. Standard y-ray spectrometry was employed for the measurement of radioactivity. Three lead-shielded HPGe detectors and one planar HPGe detector with carbon fibre window were used depending on the energy of the measured y-line. Isomeric cross section ratios of the two investigated reactions leading to the production of 58Co were determined by measurement of the complex decay curve of 58gCo. Corrections have been applied for sample irradiation and counting geometry, beam intensity variations during irradiation, background neutrons, neutron absorption and scattering, y-ray absorption and y-ray sum coincidences. The present results are compared with other measurements, and evaluated data. The experimental data are compared with STARPE-H code calculations. In some cases a comparison with TALYS code calculations is included as well.
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.
Book Synopsis Handbook on Nuclear Activation Data by : International Atomic Energy Agency
Download or read book Handbook on Nuclear Activation Data written by International Atomic Energy Agency and published by . This book was released on 1987 with total page 838 pages. Available in PDF, EPUB and Kindle. Book excerpt: The contents of this Handbook are, in general, similar to IAEA Technical Reports Series No. 156, Handbook on Nuclear Activation Cross-Sections, published in 1974. However, there are several important changes in this version, besides the inclusion of more recent data. For example, in Part 1, all the necessary information on standard reference data is now included.
Book Synopsis Thermal Neutron Activation Cross Sections by : L. Seren
Download or read book Thermal Neutron Activation Cross Sections written by L. Seren and published by . This book was released on 1944 with total page 36 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Isomeric Cross Section Ratios for Ni 58 (n,p) Co 58g, 58m Reaction Induced by Neutrons in the 13.2-15.5 MeV Energy Range by : S. Chojnacki
Download or read book Isomeric Cross Section Ratios for Ni 58 (n,p) Co 58g, 58m Reaction Induced by Neutrons in the 13.2-15.5 MeV Energy Range written by S. Chojnacki and published by . This book was released on 1965 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Data for Science and Technology by : Syed M. Qaim
Download or read book Nuclear Data for Science and Technology written by Syed M. Qaim and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 1041 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book describes the Proceedings of the International Conference on Nuclear Data for Science and Technology held at Jillich in May 1991. The conference was in a series of application oriented nuclear data conferences organized in the past under the auspices of the Nuclear Energy Agency-Nuclear Data Committee (NEANDC) and with the support of the Nuclear Energy Agency-Committee on Reactor Physics (NEACRP). It was the fIrst international conference on nuclear data held in Germany, with the scientific responsibility entrusted to the Institute of Nuclear Chemistry of the Research Centre Jillich. The scientific programme was established by the International Programme Committee in consultation with the International Advisers, and the NEA and IAEA cooperated in the organization. A total of 328 persons from 37 countries and fIve international organizations participated. The scope of these Proceedings extends to a wide range of interdisciplinary topics dealing with measu rement, calculation, evaluation and application of nuclear data, with a major emphasis on numerical data. Both energy and non-energy related applications are considered and due attention is given to some fundamental aspects relevant to the understanding of nuclear data.
Book Synopsis Calculated Neutron-activation Cross Sections for E/sub N/ D"100 MeV for a Range of Accelerator Materials by :
Download or read book Calculated Neutron-activation Cross Sections for E/sub N/ D"100 MeV for a Range of Accelerator Materials written by and published by . This book was released on 1988 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Activation problems associated with particle accelerators are commonly dominated by reactions of secondary neutrons produced in reactions of beam particles with accelerator or beam stop materials. Measured values of neutron-activation cross sections above a few MeV are sparse. Calculations with the GNASH code have been made for neutrons incident on all stable nuclides of a range of elements common to accelerator materials. These elements include B, C, N, O, Ne, Mg, Al, Si, P, S, Ar, K, Ca, Cr, Mn, Fe, Co, Ni, Cu, Zn, Zr, Mo, Nd, and Sm. Calculations were made for a grid of incident neutron energies extending to 100 MeV. Cross sections leading to the direct production of as many as 87 activation products for each of 84 target nuclide were tabulated on this grid of neutron energies, each beginning with the threshold for the product nuclide's formation. Multigrouped values of these cross sections have been calculated and are being integrated into the cross-section library of the REAC-2 neutron activation code. Illustrative cross sections are presented. 20 refs., 6 figs., 1 tab.
Book Synopsis Cyclotron Produced Radionuclides by : International Atomic Energy Agency
Download or read book Cyclotron Produced Radionuclides written by International Atomic Energy Agency and published by . This book was released on 2009 with total page 266 pages. Available in PDF, EPUB and Kindle. Book excerpt: Application of radioisotopes has shown significant growth in the past decade, and a major factor contributing towards this growth is the availability of a large number of cyclotrons dedicated to the production of radioisotopes for medical applications. Although there are many articles in journals on cyclotrons and their use for radioisotope production, there is no single source of information for beginners on radioisotope production using cyclotrons. This publication attempts to address this deficiency. Its contains chapters on accelerator technology, theoretical considerations of nuclear reactions, the technology behind targetry, techniques on preparation of targets, irradiation of targets under high beam currents, target processing and target recovery.
Book Synopsis The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy by :
Download or read book The Fission Cross Sections of 23°Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu Relative 235U at 14. 74 MeV Neutron Energy written by and published by . This book was released on 1986 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The measurement of the fission cross section ratios of nine isotopes relative to 235U at an average neutron energy of 14.74 MeV is described with particular attention to the determination of corrections and to sources of error. The results are compared to ENDF/B-V and to other measurements of the past decade. The ratio of the neutron induced fission cross section for these isotopes to the fission cross section for 235U are: 23°Th - 0.290 +- 1.9%; 232Th - 0.191 +- 1.9%; 233U - 1.132 +- 0.7%; 234U - 0.998 +- 1.0%; 236U - 0.791 +- 1.1%; 238U - 0.587 +- 1.1%; 237Np - 1.060 +- 1.4%; 239Pu - 1.152 +- 1.1%; 242Pu - 0.967 +- 1.0%. 40 refs., 11 tabs., 9 figs.
