Thermal Neutron Activation Cross-sections of Some Nuclides Used in Activation Measurements

Thermal Neutron Activation Cross-sections of Some Nuclides Used in Activation Measurements
Title Thermal Neutron Activation Cross-sections of Some Nuclides Used in Activation Measurements PDF eBook
Author Edward T. Józefowicz
Publisher
Pages 7
Release 1963
Genre
ISBN

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Thermal Neutron Activation Cross Sections

Thermal Neutron Activation Cross Sections
Title Thermal Neutron Activation Cross Sections PDF eBook
Author L. Seren
Publisher
Pages 36
Release 1944
Genre Neutrons
ISBN

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Neutron Activation Cross Sections

Neutron Activation Cross Sections
Title Neutron Activation Cross Sections PDF eBook
Author
Publisher
Pages 16
Release 1959
Genre Neutrons
ISBN

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Neutron Activation Analysis Methods for the Group VIII Elements

Neutron Activation Analysis Methods for the Group VIII Elements
Title Neutron Activation Analysis Methods for the Group VIII Elements PDF eBook
Author Charles Everett Miller (Jr)
Publisher
Pages 122
Release 1959
Genre Nuclear activation analysis
ISBN

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Thermal Neutron Activation Cross Section of Np237

Thermal Neutron Activation Cross Section of Np237
Title Thermal Neutron Activation Cross Section of Np237 PDF eBook
Author R. R. Smith
Publisher
Pages 28
Release 1955
Genre Neptunium
ISBN

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Activation Analysis

Activation Analysis
Title Activation Analysis PDF eBook
Author Zeev Alfassi
Publisher CRC Press
Pages 646
Release 1990-06-22
Genre Science
ISBN 9780849345845

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This timely publication covers prompt measurements as well as delayed activation measurements used in chemical analysis of the elements. It describes the various possibilities of activation: neutrons, charged ions, and photons. Also discussed are the advantages and disadvantages of each activation method. These volumes are important for those in geology, archaeology, biology, analytical chemistry, radioanalytical and nuclear chemistry, the semiconductor industry, and others.

Neutron Activation Cross Sections for Safety of Nuclear Power Plants

Neutron Activation Cross Sections for Safety of Nuclear Power Plants
Title Neutron Activation Cross Sections for Safety of Nuclear Power Plants PDF eBook
Author European Communities
Publisher
Pages
Release 2003
Genre
ISBN

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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.