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production in subcritical assembly Quinta. Student: Piotr Konarski - PowerPoint PPT Presentation

U-238 fission and Pu-239 production in subcritical assembly Quinta. Student: Piotr Konarski AGH University of Science and Technology Supervisor: Andrzej Wojciechowski Ph. D. Group: Laboratory of Information Technologies Outline


  1. U-238 fission and Pu-239 production in subcritical assembly ‘Quinta’. Student: Piotr Konarski AGH University of Science and Technology Supervisor: Andrzej Wojciechowski Ph. D. Group: Laboratory of Information Technologies

  2. Outline  The aim of the experiment.  Quinta assembly.  The aim of my work.  Calculations and results.  Conclusion.

  3. Project uses the results of experimental collaboration ‘Energy and transmutation of radioactive waste’ Members of a group : Russia (JINR Dubna, CPTP Atomenergomash, Moscow, Russia, Obmińsk) Belaruss, Poland, Czech Republic, Germany, France, Greece, Mongolia, Ukraine, Australia. Coordinator of experimental collaboration: prof. S.Tyutyunnikov

  4. The aim of the experiment. Quinta was designed for research the transmutation of the long-lived components of radioactive waste. Very important goal of the experimental program is to provide comprehensive benchmark data set for verification and adjustment of INC models and transport codes. Collected data will be used for design another experiment like this.

  5. Quinta assembly Assembly is constructed with natural uranium rods and 6 planes with detectors. Total mass of uranium is about 315kg. There are 3 different types of detectors used for measure of neutron flux. First one is made of natural uranium, second one contains helium-3 and the last one is made of plastic polymer CR39. Reaction of fission and capture were measured by activation methods.

  6. Geometry of Quinta assembly simulated in MCNPX. The colors on the figures means: red – natural U, green - air, blue - Al, a) b)  a) The Z-Y cross section of assembly  b) The X-Z cross section of assembly

  7. Geometry of Quinta assembly simulated in MCNPX. The colors on the figures means: red – natural U, green - air, blue - Al, pink - CR39, light blue - 3He a) b)  a) The X-Y cross section of uranium section  b) The X-Y cross section of plane with detectors

  8. The aim of my work. The goal of project is computer simulation of U-238 fission and production Pu-239 in fast neutron beam in the experiment Quinta (made in December 2013 in Dubna). Using MCNPX code (based on Monte Carlo method) has been done comparison results of calculations with experiment data.

  9. Spallation process Spallation process is source of high energy neutron. Single energetic ion can produce many fast neutrons

  10. Reactions of U-238 with neutron Pu-239 production U-238 fission

  11. Method of calculation To calculate number of reaction was used following formula: N E E dE 0 Where φ(E) density of neutron flux calculated by MCNPX, σ(E) – cross section of neutron capture and ρ is uranium density.

  12. Conclusion  Carbon ion gives more nuclear interactions per nucleus than deuteron and proton  Experimental and calculation data for carbon agree with experimental errors  Deuteron gives more nuclear interactions per one nucleon than carbon ion and proton but this domination is in range of experimental error  Experiment values are higher than calculated in most examples  For energies greater than about 1MeV fission reaction dominates  Number of reaction decrease with distance from target axis

  13. The End. Thank you for your attention.

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