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шеляговский 20.10.2017

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шеляговский 20.10.2017

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шеляговский 20.10.2017

  1. 1. Investigation of two-zone subcritical research reactor geometry and fuel composition for nuclear waste transmutation D.O. Sheliahovskyi, A.V. Nosovskyi, V.I. Gulik Institute for Safety Problems of NPP (Kyiv, Ukraine) ХІΙІ International Scientific and Technical Conference of Young Scientists and Specialists “Problems of Modern Nuclear Power Engineering” (Kharkiv, Ukraine)
  2. 2. Outline • ADS introduction; • Model of two-zone subcritical research reactor; • Serpent modeling results; • Conclusions; 2 ХІΙІ International Scientific and Technical Conference of Young Scientists and Specialists “Problems of Modern Nuclear Power Engineering” (Kharkiv, Ukraine)
  3. 3. ADS (Accelerator Driven Systems) – innovative nuclear systems which consists of a high power elementary particles accelerator, spallation target, and a subcritical core. ADS benefits: High fuel composition flexibility High safety level 3 ХІΙІ International Scientific and Technical Conference of Young Scientists and Specialists “Problems of Modern Nuclear Power Engineering” (Kharkiv, Ukraine)
  4. 4. Model of two-zone subcritical research reactor • Two zones with different neutron spectra; • Titanium target (D-T nuclear reaction); • Approximately kinetic energy of external neutrons 14 MeV. 4 ХІΙІ International Scientific and Technical Conference of Young Scientists and Specialists “Problems of Modern Nuclear Power Engineering” (Kharkiv, Ukraine)
  5. 5. Research reactor model (cross-section) Model of two-zone subcritical research reactor 5 Calculation parameters in the developed model: • diameter of the target is 5 cm; • thickness of stainless steel container wall is 1 cm; • thickness of the beryllium reflector is 5 cm; • diameter-to-height ratio of subcritical core is 1 (for neutrons leakage minimization); • External source produce 14 MeV monoenergetic neutrons; • effective neutron multiplication factor is 0.97; • total number of source neutrons is 50000; • Moderator – graphite / coolant – helium; ХІΙІ International Scientific and Technical Conference of Young Scientists and Specialists “Problems of Modern Nuclear Power Engineering” (Kharkiv, Ukraine)
  6. 6. Researched systems: System A: • Internal zone: enrichment is 10 % 235 U; radius from 10,5 cm to 43,5 cm; • External zone: enrichment is 5 % 235 U; System B: • Internal zone: enrichment is 15 % 235 U; radius from 10,5 cm to 50,5 cm; • External zone: enrichment is 3 % 235 U; Research reactor model (neutron flux image) 6 ХІΙІ International Scientific and Technical Conference of Young Scientists and Specialists “Problems of Modern Nuclear Power Engineering” (Kharkiv, Ukraine)
  7. 7. Serpent modeling results (Flux research) 7 System A System B ХІΙІ International Scientific and Technical Conference of Young Scientists and Specialists “Problems of Modern Nuclear Power Engineering” (Kharkiv, Ukraine) 0 50 100 150 200 250 10 15 20 25 30 35 40 45 Neutronflux(peroneexternalneutron) Inner zone radius, cm Flux internal external total 0 50 100 150 200 250 300 10 15 20 25 30 35 40 45 50Neutronflux(peroneexternalneutron) Inner zone radius, cm Flux internal external total
  8. 8. Serpent modeling results (Fuel cost research) 8 ХІΙІ International Scientific and Technical Conference of Young Scientists and Specialists “Problems of Modern Nuclear Power Engineering” (Kharkiv, Ukraine) System A System B 0 2 4 6 8 10 12 14 16 10 15 20 25 30 35 40 45 50 millionEuro Inner zone radius, cm Cost internal external total 0 2 4 6 8 10 12 10 15 20 25 30 35 40 45 millionEuro Inner zone radius, cm Cost internal external total
  9. 9. 9 Serpent modeling results (transmutation cross- section research) System A 0 10 20 30 40 50 60 70 80 10 15 20 25 30 35 40 45 α Inner zone radius, cm Np-237 Am-243 0 2 4 6 8 10 12 14 16 18 10 15 20 25 30 35 40 45σc,barm Inner zone radius, cm I-129 Tc-99 ХІΙІ International Scientific and Technical Conference of Young Scientists and Specialists “Problems of Modern Nuclear Power Engineering” (Kharkiv, Ukraine) 𝛼 = 𝜎𝑐/𝜎𝑓
  10. 10. Serpent modeling results (transmutation cross- section research) 0 2 4 6 8 10 12 14 16 18 10 15 20 25 30 35 40 45 50 σc,barn Inner zone radius, cm I-129 Tc-99 10 ХІΙІ International Scientific and Technical Conference of Young Scientists and Specialists “Problems of Modern Nuclear Power Engineering” (Kharkiv, Ukraine) 0 10 20 30 40 50 60 10 15 20 25 30 35 40 45 50 α Inner zone radius, cm Np-237 Am-243 𝛼 = 𝜎𝑐/𝜎𝑓 System B
  11. 11. Conclusions Optimization calculations for both systems have shown that increasing internal zone volume leads to: • increasing neutron flux in the internal zone; • improving transmutation factor for minor actinides (MA); • reducing neutron flux in the external zone; • increasing fuel composition сost of the entire subcritical system; Comparing systems A (10% enriched 235U) and B (15% enriched 235U) have shown: • transmutation factor for MA(237Np, 237Am) is better for system B; • capture cross-sections for long-lived fission products LFP (129I and 99Tc) are better for system B; • system B fuel composition is more expensive than system A; 11 ХІΙІ International Scientific and Technical Conference of Young Scientists and Specialists “Problems of Modern Nuclear Power Engineering” (Kharkiv, Ukraine)
  12. 12. Thank you for attention More information: Dmytro Sheliahovskiy shelagovskii@gmail.com Volodymyr Gulik volodymyr.gulik@gmail.com 12 ХІΙІ International Scientific and Technical Conference of Young Scientists and Specialists “Problems of Modern Nuclear Power Engineering” (Kharkiv, Ukraine)

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