1 / 13

Transmutation of spent nuclear fuel

Transmutation of spent nuclear fuel. Jaroslav Šoltés 1 Jiří Skalička 2 1 – Czech Technical University, Prague 2 – Brno University of Technology 3 – Joint Institute of Nuclear Research, Dubna. Supervisor: Lukáš Závorka 3. Main goals of transmutation.

jena
Download Presentation

Transmutation of spent nuclear fuel

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript

  1. Transmutation of spent nuclear fuel Jaroslav Šoltés1 Jiří Skalička2 1 – Czech Technical University, Prague 2 – Brno University of Technology 3 – Joint Institute of Nuclear Research, Dubna Supervisor: Lukáš Závorka3

  2. Main goals of transmutation • Burnup of minor actinides in spent nuclear fuel to reduce its radioactivity (Am, Cm) • Converting fertile isotopes to fissile isotopes (232Th, 238U)

  3. Accelarator driven systems • High energy and intensive neutron source is needed • They cannot be obtained via standard thermal or fast fission in a reactor • Spallation reactions are required which can be achieved only by using an accelerator driven system (ADS)

  4. Accelerator driven systems

  5. Neutron reactions in the ADS core • Fission of heavy nuclei (Am, Cm, U, Th, Pu) • Neutron capture on Th, U and fissile isotopes creation • (n,xn) on Th creating additional neutrons

  6. QUINTA experiment

  7. HPGe γ-spectrometer Ortec

  8. Measurements carried out • Time of irradiation: 16 h • Number of measurements: 8 • Measured 2 h, 3 h, 11 h, 28 h, 36 h, 50 h, 45 d and 105 d after irradiation

  9. Samples evaluation • Identification of dominant gamma peaks in spectra • Energy calibration • Non-linearity correction • Background correction • Single escape and double escape peak correction • Effectivity calibration correction • Isotopes identification

  10. Identified isotopes • Fission products: 85mKr, 85mSr, 85mY, 87Kr, 88Kr, 88Rb, 90mY, 91Sr, 92Sr, 92Y, 93Y, 95Nb, 95mTc, 96Nb, 97Zr, 99Mo, 103Ru, 105Ru, 105Rh, 123I, 127Cs, 127Sb, 128Sb, 131Ba, 131I, 132Cs, 132I, 132Te, 133I, 134I, 135I, 135Xe, 138Cs, 139Ba, 139Ce, 140Ba, 140La, 141Ce, 142La, 143Ce • Decay products of (n,xn) reactions isotopes: 210Po, 210mBi, 213Bi, 214Pb, 219Rn, 223Ra, 224Ac, 226Ac, 226Ra, 227Ac, 230Th • Activation product of 232Th: 233Pa

  11. Detected nuclei count Nuclei count: 232Th-11: 3,52*1020 232Th-12: 3,64*1020 233Pa-11: 7,72*108 233Pa-12: 4,46*108

  12. Conclusion • Detected fission products indicate fast neutron fission of the target 232Th • Detected isotopes of 233Pa which beta-decays into 233U show effective fissile fuel breeding possibilities ADS • (n,xn) reactions are important additional source to neutron balance • 232Th is therefore ideal candidate for the ADS breeding zone

  13. Thank you for your attention soltes.jaro@gmail.com jiri.skalicka@gmail.com

More Related