Measurement of the fission cross section of232U for neutron energies in the range 0.06?7.40 MeV

Fursov, B. I.; Baranov, E. Yu.; Klemyshev, M. P.; Samylin, B. F.; Smirenkin, G.N.; Turchin, Yu. M.

doi:10.1007/bf01122291

Cited by 10 publications

(2 citation statements)

References 1 publication

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“…The fission cross sections of JENDL-3.3 for 232 U are constant below 5 MeV. However, the present calculation follows the data of Fursov et al 43) The theoretical calculation provides useful information that can be used to eliminate the experimental data having no physical basis.…”

Section: Fission Cross Sectionsmentioning

confidence: 86%

Development of a Comprehensive Code for Nuclear Data Evaluation, CCONE, and Validation Using Neutron-Induced Cross Sections for Uranium Isotopes

Iwamoto

2007

Journal of Nuclear Science and Technology

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A new comprehensive code for nuclear data evaluation, CCONE, has been developed for the evaluation of nuclear data for actinides. Neutron-induced reaction cross sections for uranium isotopes (A = 232, 233, 234, 235, 236, 237, 238) were analyzed for incident energies from 10 keV to 20 MeV using CCONE in order to validate its capability. Reproducibility of the cross section calculations for various reactions such as total, fission, capture, and (n, 2n) was tested using simple parameterization. The calculated cross sections and neutron emission spectra show good agreement with the experimental data.

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Section: Fission Cross Sectionsmentioning

confidence: 86%

Development of a Comprehensive Code for Nuclear Data Evaluation, CCONE, and Validation Using Neutron-Induced Cross Sections for Uranium Isotopes

Iwamoto

2007

Journal of Nuclear Science and Technology

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“…Because for n+ 232 U reaction the only reliable experimental information is a single set of experimental data for fission [141], for the fission barrier parameters of the compound nucleus 233 U we relied on those derived from the simultaneous fit of 233 U(n,nf), 234 U(n,2nf) and 235 U(n,3nf) cross sections. The procedure was extended for heavier isotopes by adjusting the parameters used for 234 U(n,f) to fit the 236 U(n,f) experimental cross section.…”

Section: Fission Cross Sectionsmentioning

confidence: 99%

Modelling Neutron-induced Reactions on 232–237U from 10 keV up to 30 MeV

Sin

Capote

Herman

et al. 2017

Nuclear Data Sheets

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Comprehensive calculations of cross sections for neutron-induced reactions on 232−237 U targets are performed in the 10 keV-30 MeV incident energy range with the code EMPIRE-3.2 Malta. The advanced modelling and consistent calculation scheme are aimed at improving our knowledge of the neutron scattering and emission cross sections, and to assess the consistency of available evaluated libraries for light uranium isotopes. The reaction model considers a dispersive optical potential (RIPL 2408) that couples from five (even targets) to nine (odd targets) levels of the groundstate rotational band, and a triple-humped fission barrier with absorption in the wells described within the optical model for fission. A modified Lorentzian model (MLO) of the radiative strength function and Enhanced Generalized Superfluid Model nuclear level densities are used in Hauser-Feschbach calculations of the compound-nuclear decay that include width fluctuation corrections. The starting values for the model parameters are retrieved from RIPL. Excellent agreement with available experimental data for neutron emission and fission is achieved, giving confidence that the quantities for which there is no experimental information are also accurately predicted. Deficiencies in existing evaluated libraries are highlighted.

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Probability of nuclear fisson and effective fisson cross sections

Zamyatnin¹,

Konovalov²

Low Energy Neutrons and Their Interaction With Nuclei and Matter. Part 1

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Measurement of the fission cross section of232U for neutron energies in the range 0.06?7.40 MeV

Cited by 10 publications

References 1 publication

Development of a Comprehensive Code for Nuclear Data Evaluation, CCONE, and Validation Using Neutron-Induced Cross Sections for Uranium Isotopes

Development of a Comprehensive Code for Nuclear Data Evaluation, CCONE, and Validation Using Neutron-Induced Cross Sections for Uranium Isotopes

Modelling Neutron-induced Reactions on 232–237U from 10 keV up to 30 MeV

Probability of nuclear fisson and effective fisson cross sections

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