Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
-
Ö. Sönmez
and
O. Karaman
Abstract
Level density models have increasing importance to gain more in-depth into the nature of nuclear reactions. Many novel and advanced medical application use radioisotopes, which are produced with nuclear reactions. In this study, the effect of the level density parameters of the nucleus on the cross sections of neutron-fission reactions for 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei were investigated for up to 20 MeV neutrons. TALYS 1.8 software was used to calculate the cross-sections of neutron-fission reactions for different level density parameters. The calculations were compared with the EXFOR nuclear data library and the level density parameters, and the closest fit were searched. As outputs of the study, the effect of selection of level density parameter on cross section calculations was observed. The theoretically obtained data were compared with the experimental data taken from the literature. The results are presented graphically for better interpretation.
Kurzfassung
Niveaudichtemodelle haben zunehmende Bedeutung, um den Ablauf von Kernreaktionen besser zu verstehen. Viele neuartige und fortschrittliche medizinische Anwendungen nutzen Radioisotope, die durch Kernreaktionen erzeugt werden. In dieser Studie wurde der Einfluss der Niveaudichte-Parameter des Kerns auf die Wirkungsquerschnitte von Neutronen-Spaltreaktionen für die Kerne 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu und 247Cm für Neutronen mit einer Energie von bis zu 20 MeV untersucht. Dabei wurde die Software TALYS 1.8 verwendet, um die Wirkungsquerschnitte der Neutronenspaltreaktionen für verschiedene Niveaudichteparameter zu berechnen. Die Berechnungen wurden mit der EXFOR-Kerndatenbibliothek und den Niveaudichteparametern verglichen und es wurde die beste Übereinstimmung gesucht. Als Ergebnisse der Studie wurde die Auswirkung der Auswahl der Niveaudichteparameter auf die Querschnittsberechnungen bestimmt. Die theoretisch erhaltenen Daten wurden mit den experimentellen Daten aus der Literatur verglichen. Die Ergebnisse werden zur besseren Interpretation grafisch dargestellt.
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Articles in the same Issue
- Frontmatter
- The simulation research on the natural circulation operation characteristic of FNPP in rolling and inclined condition
- Establishment of analysis methodology of RADTRAD for Maanshan PWR ATWS
- Calendar of Events
- CFD simulation of subcooled boiling flow in PWR 5 ⨯ 5 rod bundle
- Effectiveness assessment of improvement measures in physical protection system monitoring center
- A study on accumulator analysis for the valve performance evaluation system of nuclear power plants
- Calculation studies of coated particles performance in sodium-cooled fast reactor
- Effect of using graphene/water based nanofluid on heat transfer in heat exchangers with rotating straight inner tube
- Radiation shielding properties of mortars containing heavyweight particles
- Improvement of the passive efficiency calibration of the segmented gamma scanner
- Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
- Establishment of analysis methodology for ionizing mattresses using RESRAD-BUILD code
- Editorial
Articles in the same Issue
- Frontmatter
- The simulation research on the natural circulation operation characteristic of FNPP in rolling and inclined condition
- Establishment of analysis methodology of RADTRAD for Maanshan PWR ATWS
- Calendar of Events
- CFD simulation of subcooled boiling flow in PWR 5 ⨯ 5 rod bundle
- Effectiveness assessment of improvement measures in physical protection system monitoring center
- A study on accumulator analysis for the valve performance evaluation system of nuclear power plants
- Calculation studies of coated particles performance in sodium-cooled fast reactor
- Effect of using graphene/water based nanofluid on heat transfer in heat exchangers with rotating straight inner tube
- Radiation shielding properties of mortars containing heavyweight particles
- Improvement of the passive efficiency calibration of the segmented gamma scanner
- Investigation of level density parameter dependence for some 233U, 235U, 237U, 239U, 249Cf, 251Cf, 237Pu and 247Cm nuclei in neutron fission cross sections with the incident energy up to 20 MeV
- Establishment of analysis methodology for ionizing mattresses using RESRAD-BUILD code
- Editorial
