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 V. Semkova
Publisher
Pages 35
Release 2003
Genre
ISBN 9789289460958

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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.

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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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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American National Standard, Neutron and Gamma-ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants

American National Standard, Neutron and Gamma-ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants
Title American National Standard, Neutron and Gamma-ray Cross Sections for Nuclear Radiation Protection Calculations for Nuclear Power Plants PDF eBook
Author American Nuclear Society
Publisher
Pages 16
Release 1983
Genre Fission cross sections
ISBN

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Nuclear Science Abstracts

Nuclear Science Abstracts
Title Nuclear Science Abstracts PDF eBook
Author
Publisher
Pages 860
Release 1973
Genre Nuclear energy
ISBN

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Reports to the AEC Nuclear Cross Sections Advisory Group

Reports to the AEC Nuclear Cross Sections Advisory Group
Title Reports to the AEC Nuclear Cross Sections Advisory Group PDF eBook
Author
Publisher
Pages 44
Release 1956-09
Genre Nuclear physics
ISBN

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