Author: G. D. James
Publisher: Elsevier
ISBN: 1483189767
Category : Science
Languages : en
Pages : 294
Book Description
Nuclear Fission and Neutron-Induced Fission Cross-Sections is the first volume in a series on Neutron Physics and Nuclear Data in Science and Technology. This volume serves the purpose of providing a thorough description of the many facets of neutron physics in different fields of nuclear applications. This book also attempts to bridge the communication gap between experts involved in the experimental and theoretical studies of nuclear properties and those involved in the technological applications of nuclear data. This publication will be invaluable to those interested in studying nuclear fission and neutron-induced fission cross-sections, as well as other relevant concepts.
Nuclear Fission and Neutron-Induced Fission Cross-Sections
Author: G. D. James
Publisher: Elsevier
ISBN: 1483189767
Category : Science
Languages : en
Pages : 294
Book Description
Nuclear Fission and Neutron-Induced Fission Cross-Sections is the first volume in a series on Neutron Physics and Nuclear Data in Science and Technology. This volume serves the purpose of providing a thorough description of the many facets of neutron physics in different fields of nuclear applications. This book also attempts to bridge the communication gap between experts involved in the experimental and theoretical studies of nuclear properties and those involved in the technological applications of nuclear data. This publication will be invaluable to those interested in studying nuclear fission and neutron-induced fission cross-sections, as well as other relevant concepts.
Publisher: Elsevier
ISBN: 1483189767
Category : Science
Languages : en
Pages : 294
Book Description
Nuclear Fission and Neutron-Induced Fission Cross-Sections is the first volume in a series on Neutron Physics and Nuclear Data in Science and Technology. This volume serves the purpose of providing a thorough description of the many facets of neutron physics in different fields of nuclear applications. This book also attempts to bridge the communication gap between experts involved in the experimental and theoretical studies of nuclear properties and those involved in the technological applications of nuclear data. This publication will be invaluable to those interested in studying nuclear fission and neutron-induced fission cross-sections, as well as other relevant concepts.
Summary of Neutron-induced Fission Cross Sections
Author: R. L. Henkel
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 28
Book Description
Publisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages : 28
Book Description
Fluctuations in Neutron-Induced Fission Cross Sections
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Category :
Languages : en
Pages :
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Category :
Languages : en
Pages :
Book Description
Reports to the AEC Nuclear Cross Sections Advisory Group
Author:
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Category : Nuclear physics
Languages : en
Pages : 72
Book Description
Publisher:
ISBN:
Category : Nuclear physics
Languages : en
Pages : 72
Book Description
Neutron-induced Fission Cross Sections of 233U, 234U, 236U, and 238U with Respect to 235U.
Author:
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ISBN:
Category :
Languages : en
Pages :
Book Description
Publisher:
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Category :
Languages : en
Pages :
Book Description
Neutron Cross Sections
Author: Victoria McLane
Publisher: Elsevier
ISBN: 0323142222
Category : Science
Languages : en
Pages : 850
Book Description
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.
Publisher: Elsevier
ISBN: 0323142222
Category : Science
Languages : en
Pages : 850
Book Description
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.
Tables of Neutron-Induced Fission Cross Section for Various Pu, U, and Th Isotopes, Deduced from Measured Fission Probabilites
Author: W. Younes
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Cross sections for neutron-induced fission of {sup 231,233}Th, {sup 234,235,236,237,239}U, and {sup 240,241,243}Pu are presented in tabular form for incident neutron energies of 0.1 {le} E{sub n}(MeV) {le} 2.5. The cross sections were obtained by converting measured fission probabilities from (t, pf) reactions on mass-A targets to (n, f) cross sections on mass-A + 1 neutron targets, by using modeling to compensate for the differences in the reaction mechanisms. Data from Britt et al. were used for the {sup 234}U(t, pf) reaction, from Cramer et al. for the {sup 230,232}Th(t, pf), {sup 236,238}U(t, pf), and {sup 240,242}Pu(t, pf) reactions, and from Britt et al. for the {sup 233,235}U(t, pf) and {sup 239}Pu(t, pf) reactions. The fission probabilities P{sub (t, pf)}(E{sub x}), measured as a function of excitation energy E{sub x} of the compound system formed by the (t, p) reaction, are listed in the tables with the corresponding deduced cross sections as a function of incident neutron energy E{sub n}, {sigma}{sub (n, f)}(E{sub n}). The excitation energy and incident neutron energy are related by E{sub x} = E{sub n} + B{sub n}, where B{sub n}, where B{sub n} is the neutron binding energy. Comparison with ENDF/B-VI evaluations of the well-measured {sup 234,235,236}U(n, f) and {sup 240,241}Pu(n, f) cross sections confirms the accuracy of the present results within a 10% standard deviation above E{sub n} = 1 MeV. Below E{sub n} = 1 MeV, localized deviations of at most {+-} 20% are observed.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Cross sections for neutron-induced fission of {sup 231,233}Th, {sup 234,235,236,237,239}U, and {sup 240,241,243}Pu are presented in tabular form for incident neutron energies of 0.1 {le} E{sub n}(MeV) {le} 2.5. The cross sections were obtained by converting measured fission probabilities from (t, pf) reactions on mass-A targets to (n, f) cross sections on mass-A + 1 neutron targets, by using modeling to compensate for the differences in the reaction mechanisms. Data from Britt et al. were used for the {sup 234}U(t, pf) reaction, from Cramer et al. for the {sup 230,232}Th(t, pf), {sup 236,238}U(t, pf), and {sup 240,242}Pu(t, pf) reactions, and from Britt et al. for the {sup 233,235}U(t, pf) and {sup 239}Pu(t, pf) reactions. The fission probabilities P{sub (t, pf)}(E{sub x}), measured as a function of excitation energy E{sub x} of the compound system formed by the (t, p) reaction, are listed in the tables with the corresponding deduced cross sections as a function of incident neutron energy E{sub n}, {sigma}{sub (n, f)}(E{sub n}). The excitation energy and incident neutron energy are related by E{sub x} = E{sub n} + B{sub n}, where B{sub n}, where B{sub n} is the neutron binding energy. Comparison with ENDF/B-VI evaluations of the well-measured {sup 234,235,236}U(n, f) and {sup 240,241}Pu(n, f) cross sections confirms the accuracy of the present results within a 10% standard deviation above E{sub n} = 1 MeV. Below E{sub n} = 1 MeV, localized deviations of at most {+-} 20% are observed.
Measurement of the Neutron-induced Fission Cross Section of 241Pu Relative to 235U from 0.001 to 30 MeV.
Author:
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ISBN:
Category :
Languages : en
Pages :
Book Description
The ratio of the neutron-induced fission cross sections of 241Pu relative to that of 235U was measured with fission ionization chambers at the LLL 100-MeV electron linear accelerator. The time-of-flight technique was used to measure the cross-section ratio as a function of neutron energy from 0.001 to 30 MeV. The continuous energy spectrum of the neutron source allowed us to cover the entire energy range in one measurement. Pulse height distributions were also measured as functions of energy over broad energy bands. These data were used to estimate the energy variation in the efficiency to be less than 0.75 percent. The threshold cross-section method normalized the ratio independent of other cross-section measurements to 1.268 +- 0.022 in the interval 1.75 to 4.00 MeV. The ratio was also taken to thermal neutron energy where it was normalized to evaluated thermal fission cross sections and the resulting ratio in the 1.75- to 4.00-MeV interval was 1.242 +- 0.021. Corrected for the impurities in the 241Pu sample, the average of these two values resulted in a $sup 241$Pu:235U fission cross-section ratio of 1.251 +- 0.016 for the normalization interval. Typical energy resolution is 5 percent at 20.0, 1.0, and 0.1 MeV. Most of the data have counting uncertainties smaller than 4 percent, expressed as a standard deviation. Systematic errors are discussed, and current results are compared with previous measurements. Tables of our data are included. (9 tables, 8 figures) (auth).
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The ratio of the neutron-induced fission cross sections of 241Pu relative to that of 235U was measured with fission ionization chambers at the LLL 100-MeV electron linear accelerator. The time-of-flight technique was used to measure the cross-section ratio as a function of neutron energy from 0.001 to 30 MeV. The continuous energy spectrum of the neutron source allowed us to cover the entire energy range in one measurement. Pulse height distributions were also measured as functions of energy over broad energy bands. These data were used to estimate the energy variation in the efficiency to be less than 0.75 percent. The threshold cross-section method normalized the ratio independent of other cross-section measurements to 1.268 +- 0.022 in the interval 1.75 to 4.00 MeV. The ratio was also taken to thermal neutron energy where it was normalized to evaluated thermal fission cross sections and the resulting ratio in the 1.75- to 4.00-MeV interval was 1.242 +- 0.021. Corrected for the impurities in the 241Pu sample, the average of these two values resulted in a $sup 241$Pu:235U fission cross-section ratio of 1.251 +- 0.016 for the normalization interval. Typical energy resolution is 5 percent at 20.0, 1.0, and 0.1 MeV. Most of the data have counting uncertainties smaller than 4 percent, expressed as a standard deviation. Systematic errors are discussed, and current results are compared with previous measurements. Tables of our data are included. (9 tables, 8 figures) (auth).
Evaluation of Fission Cross Sections and Covariances 233U, 235U, 238U, 239Pu, 240Pu, and 241Pu
Author:
Publisher:
ISBN:
Category : Cross sections (Nuclear physics)
Languages : en
Pages : 88
Book Description
Publisher:
ISBN:
Category : Cross sections (Nuclear physics)
Languages : en
Pages : 88
Book Description
Measurement of Neutron-Induced Nuclear Reaction Cross Sections on Fission-Product Nuclides
Author:
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Category :
Languages : en
Pages :
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Publisher:
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Category :
Languages : en
Pages :
Book Description