G. Perdikakis1,2, C. T. Papadopoulos1, R. Vlastou1, A. Lagoyannis2, A

Slides:

Advertisements

Similar presentations

NUCLEAR REACTION MODELS FOR SYSTEMATIC ANALYSIS OF FAST NEUTRON INDUCED (n,p) REACTION CROSS SECTIONS M.Odsuren, J.Badamsambuu, G.Khuukhenkhuu Nuclear.

Advertisements

The fission of a heavy fissile nucleus ( A, Z ) is the splitting of this nucleus into 2 fragments, called primary fragments A’ 1 and A’ 2. They are excited.

Contributions to Nuclear Data by Radiochemistry Division, BARC

Modeling of Photonuclear Reactions & Transmutation of Long-lived Nuclear Waste in High Photon Fluxes M.-L. GIACRI-MAUBORGNE, D. RIDIKAS, J.-C.

Experimental Determination of Neutron Cross Sections of Yttrium by Activation Method by Barbara Geier Supervisors: Assoc. Prof Dr. Wolfgang Sprengel RNDr.

3 rd Annual INPP Meeting 17/6/2013 M. Axiotis Institute of Nuclear & Particle Physics NCSR “Demokritos” New Detector at the Tandem Laboratory of INPP for.

Kazimierz What is the best way to synthesize the element Z=120 ? K. Siwek-Wilczyńska, J. Wilczyński, T. Cap.

L. Tassan-Got – IPN Orsay Nuclear data and reactor physics Radiotoxicity and spent fuel.

Measurements of cross-sections of neutron threshold reactions and their usage in high energy neutron measurements Ondřej Svoboda Nuclear Physics Institute,

Production of elements near the N = 126 shell in hot fusion- evaporation reactions with 48 Ca, 50 Ti, and 54 Cr projectiles on lanthanide targets Dmitriy.

E.Chiaveri on behalf of the n_TOF Collaboration n_TOF Collaboration/Collaboration Board Lisbon, 13/15 December 2011 Proposal for Experimental Area 2(EAR-2)

Nuclear Data for ADS and Transmutation Joint TREND/SANDAT proposal for FP6 ADOPT- Meeting, Dec E. Gonzalez-Romero (CIEMAT) Introduction Sensitivity.

Applications of neutron spectrometry Neutron sources: 1) Reactors 2) Usage of reactions 3) Spallation sources Neutron show: 1) Where atoms are (structure)

Α - capture reactions using the 4π γ-summing technique Α. Lagoyannis Institute of Nuclear Physics, N.C.S.R. “Demokritos”

A scintillation detector for neutrons below 1 MeV with gamma-ray rejection Scintillators are 3 mm BC408, 10 layers total Adjacent layers are optically.

Future usage of quasi-infinite depleted uranium target (BURAN) for benchmark studies Pavel Tichý Future usage of quasi-infinite depleted uranium target.

The Status of Nuclear Data above 20 MeV Masayoshi SUGIMOTO, Tokio FUKAHORI Japan Atomic Energy Agency IAEA’s Technical Meeting on Nuclear Data Libraries.

Simulations of Accelerator Driven Systems (ADS) Aleksander Polanski Joint Institute for Nuclear Research, Dubna, Russia. The Andrzej Soltan Institute for.

High-spin structures in the 159 Lu nucleus Jilin University, China Institute of Atomic Energy 李聪博 The 13th National Nuclear Structure Conference of China.

Studies of neutron cross-sections by activation method in Nuclear Physics Institute Řež and in The Svedberg Laboratory Uppsala and experimental determination.

Incomplete fusion studies near Coulomb barrier Pragya Das Indian Institute of Technology Bombay Powai, Mumbai , India.

Kazimierz 2011 T. Cap, M. Kowal, K. Siwek-Wilczyńska, A. Sobiczewski, J. Wilczyński Predictions of the FBD model for the synthesis cross sections of Z.

NATIONAL TECHNICAL UNIVERSITY OF ATHENS DEPARTMENT OF PHYSICS A Detailed Study of the 10,11 B(d,α) and 10,11 B(d,p) Reactions at Detector Angles between.

Measurements of the (n,xn) reactions cross sections using new digital methods. Habib Karam Group GRACE.

NATIONAL TECHNICAL UNIVERSITY OF ATHENS DEPARTMENT OF PHYSICS NRA studies at the INP Tandem: Present status and perspectives M. Kokkoris 1, C. T. Papadopoulos.

Monte Carlo methods in ADS experiments Study for state exam 2008 Mitja Majerle “Phasotron” and “Energy Plus Transmutation” setups (schematic drawings)

Systematic studies of neutrons produced in the Pb/U assembly irradiated by relativistic protons and deuterons. Vladimír Wagner Nuclear physics institute.

Recent improvements in the GSI fission model

Cross-sections of Neutron Threshold Reactions Studied by Activation Method Nuclear Physics Institute, Academy of Sciences of Czech Republic Department.

Studies of Helium proportional counters response on fast neutrons, at NCSR “Demokritos” M. Zamani, M. Manolopoulou, S. Stoulos, M. Fragopoulou School of.

ThEC13, Geneva, 28th-31st Oct., 2013 C. H. Pyeon, Kyoto Univ. 1 Cheolho Pyeon Research Reactor Institute, Kyoto University, Japan

A CHALLENGE FOR SUSTAINABLE, CLEAN ENERGY C.Borcea

Lawrence Livermore National Laboratory LLNL-PRES-xxxxxx 1 LLNL-PRES-XXXXXX This work was performed under the auspices of the U.S. Department of Energy.

Experimental Studies of Spatial Distributions of Neutrons Produced by Set-ups with Thick Lead Target Irradiated by Relativistic Protons Vladimír Wagner.

Ondřej Svoboda Nuclear Physics Institute, Academy of Sciences of Czech Republic Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical.

Neutron cross-sections measurement at the facility at CERN Students’coffee – 26th meeting, Tuesday 28 October 2014, D02-BE Auditorium Prevessin Massimo.

Fission cross sections and the dynamics of the fission process F. -J

CERN-INTC /INTC-P-415 Tackling the s-process stellar neutron density via the 147 Pm(n,  ) reaction Spokespersons: C. Guerrero (U. Sevilla) and.

Neutron Capture Cross Sections from 1 MeV to 2 MeV by Activation Measurements Korea Institutes of Geoscience and Mineral Resource G.D.Kim, T.K.Yang, Y.S.Kim,

Mitja Majerle for the “Energy Plus Transmutation” collaboration.

Ondřej Svoboda Nuclear Physics Institute, Academy of Sciences of Czech Republic Department of Nuclear Reactors, Faculty of Nuclear Sciences and Physical.

Neutron production in Pb/U assembly irradiated by deuterons at 1.6 and 2.52 GeV Ondřej Svoboda Nuclear Physics Institute, Academy of Sciences of Czech.

C. M. Folden III Cyclotron Institute, Texas A&M University NN2012, San Antonio, Texas May 31, 2012.

Neutron production in Pb/U assembly irradiated by 1.26 AGeV deuterons. First experimental results Ondřej Svoboda Neutron production in Pb/U assembly irradiated.

ObservedChannel181Hf180Hf(n,γ)181Hf180mHf180Hf(n,n')180mHf179m2Hf180Hf(n,2n)179m2Hf179Hf(n,n')179m2Hf175Hf176Hf(n,2n)175Hf173Hf174Hf(n,2n)173Hf The Astrophysical.

9 th session of the AER Working Group “f “ - Spent Fuel Transmutations Simulations of experimental “ADS” Mitja Majerle, Gael de Cargouet Nuclear Physics.

4th International Summer School « Nuclear Physics Methods and Accelerators in Biology and Medicine » Monte-Carlo simulations : FLUKA vs. MCNPX Maxime ODEN.

Measurement of the 240 Pu(n,f) reaction cross-section at the CERN n_TOF facility EAR-2 47 th Meeting of the INTC CERN, June 25, 2014 A. Tsinganis 1, N.

Neutron production and iodide transmutation studies using intensive beam of Dubna Phasotron Mitja Majerle Nuclear Physics Institute of CAS Řež, Czech republic.

Three years of cross-section measurements of (n,xn) threshold reactions at TSL Uppsala and NPI Řež O. Svoboda, A. Krása, A. Kugler, M. Majerle, J. Vrzalová,

Christos Lamboudis HEP April. Athens Study of MDT response to neutrons and possible ageing effects Do we really need to worry about neutrons? Do.

Comparison of neutron production on lead-uranium setup irradiated by protons and deuterons with different energies Ondřej Svoboda Nuclear Physics Institute,

Transmutation of 129 I with high energy neutrons produced in spallation reactions induced by protons in massive target V.HENZL Nuclear Physics Institute.

Investigation of the proton-induced reactions on natural molybdenum.

Compound nuclear reaction cross sections from surrogate measurements

on behalf of the n_TOF Collaboration

Transmutation of spent nuclear fuel

at TSL high energy neutron facility

Measurement of the fission cross-section of 240Pu and 242Pu at CERN’s n_TOF facility CERN-INTC , INTC-P-280 Spokespersons: M. Calviani (CERN),

Cross-section Measurements of (n,xn) Threshold Reactions

Transmutation of 129I with high energy neutrons produced in spallation reactions induced by protons in massive target V. HENZL1,*, D. HENZLOVA1, A. KUGLER1,

for collaboration “Energy plus transmutation”

Pebble Bed Reactors for Once Trough Nuclear Transmutation

Mitja Majerle NPI CAS Řež, Czech Republic

Seminární soustředění společného doktorského projektu UTEF ČVUT Praha a ÚJF AVČR Řež Transmutation studies on JINR Dubna Phasotron Mitja Majerle.

Performed experiments Nuclotron – set up ENERGY PLUS TRANSMUTATION

Neutron production in Pb/U assembly irradiated by p+, d+ at 0. 7 – 2

LAHET code simulations in comparison with bare Pb spallation target experiment Daniela Henzlova.

O. Svoboda, A. Krása, A. Kugler, M. Majerle, J. Vrzalová, V. Wagner

Presentation transcript:

Measurement of the 241Am(n,2n) reaction cross section using the activation method G. Perdikakis1,2, C. T. Papadopoulos1, R. Vlastou1, A. Lagoyannis2, A. Spyrou2, M. Kokkoris1, S. Galanopoulos1, N. Patronis1, D. Karamanis3, Ch. Zarkadas2, G. Kalyva2, and S. Kossionides2 n_TOF Collaboration 1 Department of Physics, National Technical University of Athens, Athens, Greece 2Institute of Nuclear Physics, NCSR “Demokritos”, Athens, Greece 3 Department of Physics, University of Ioannina, Ioannina, Greece G. Perdikakis

Outline of the talk Motivation Experimental Analysis Results for 241Am(n,2n) Theoretical Calculations (in progress) Other reactions studied – Future Plans G. Perdikakis

Not enough experimental data ! Transmutation of MAs - Important Reaction Channels Neutron emission channels σ(n,xn) Fission Channels σ(n,xnf) Not enough experimental data ! Theoretical Predictions Experimental Investigation of Theoretical Model Parametres required G. Perdikakis

241Am: One of the most abundant isotopes in nuclear waste and one of the most radiotoxic elements Existing Data G. Perdikakis

Energy Range of Interest: 241Am(n,2n)240Am Energy Range of Interest: 8-12 MeV Να σημειώσω το κατώφλιο G. Perdikakis

Monoenergetic Neutron Beams @ INP “Demokritos” 5.5MV Tandem VdG p+ or d+ beam Shielding wall ~ 105 n/cm2s 7Li(p,n)7Be 150 – 650 keV ~ 106 n/cm2s 2H(d,n)3He 5 – 12 MeV ~ 105 n/cm2s 3H(d,n)4He 16 – 20 MeV G. Perdikakis

The Activation Target 3mm Pb shield 27 Al foil n Beam 37 GBq 241 Am target Stainless Steel G. Perdikakis

Irradiation Setup 2 m Pb HPGe D filled Gas Cell d+ ΔΕn: < 100 keV 9cm ΔΕn: < 100 keV n Beam 241Am Target 2 m Parafin BF3 Neutron Counter G. Perdikakis

Outline of the Reaction 241Am(n,2n)240Am Fission E,J,π 3n+239Am n T1/2=50.8h 2n+240Am n+241Am n+241Am γ 242Am 240Pu Most Intense γ-rays: 5 days of irradiation for each beam energy ! 987.8 keV (I=73%) 888.8 keV (I=25%) G. Perdikakis

HPGe spectrum @ 10.6 MeV 987.8 keV 240Am 154Eu 1014.7 keV 241Am 984.5 keV 238Np +154Eu 955.7 keV 241Am 154Eu @ 10.6 MeV

Reaction Cross Section G. Perdikakis

Results G. Perdikakis

G. Perdikakis et al. , Phys. Rev. C - In press Results G. Perdikakis

Outline of the Reaction 241Am(n,2n)240Am Fission E,J,π 3n+239Am n T1/2=50.8h 2n+240Am n+241Am n+241Am γ 242Am 240Pu Hauser Feshbach: Preequilibrium contribution : Exciton Model STAPRE/F G. Perdikakis

The double-humped fission barrier ρΝ ρΑ ρΒ Saddle A states Saddle B states Normal states Fission n n+X ħωΑ ħωΒ UA UB βΝ βΑ βΒ scission Deformation, β G. Perdikakis `

Main parametres of the calculation Level Density, ρ(U,J), at the saddles and at normal deformation Transmission Coefficients for neutrons,Τn Coupled Channels OMP for actinides (Ignatyuk et. al. Sov. J. Nucl. Phys. 51, (5), 1990) Fission Barrier Parametre UA,UB,ħωΑ,ħωΒ Deduced from experimental data (V. M. Maslov. RIPL-1 Handbook. TEXDOC-000, IAEA, Vienna, 1998, Ch. 5.) G. Perdikakis

Generalized Superfluid Model of the nucleus Shell, Superfluid pairing and Collective effects, important for the calculation a=ã[1+δw·f(U-Econd)] Generalized Superfluid Model of the nucleus Ignatyuk et al, Sov. J. Nucl. Phys 29, (4), 1979 G. Perdikakis

241Am(n,F) Results Preliminary !!! 241Am(n,2n) G. Perdikakis

Conclusions Other measurements Measurement of the 241Am(n,2n) reaction @ En = 8.8 – 11.4 MeV Theoretical calculations in progress 241Am(n,2n) 241Am(n,F) Other measurements 232Th(n,2n) D. Karamanis et al. NIM A 505, 381, (2003) n-induced reactions on Ge, Hf and Ir isotopes In progress 237Np(n,2n) To be done G. Perdikakis

THE END

Results Preliminary !!! 241Am(n,2n) G. Perdikakis

Conclusions and Future Perspectives Systematic Experimental Investigation of 241Am(n,2n) Reaction Cross Section, for the first time Consistent Theoretical Description of 241Am(n,2n) Reaction, in Reasonable Agreement with Experimental Data. Experimental Investigation to be Continued at Lower Energies Improvement of Theoretical Description over the whole energy range

241Am(n,2n)240Am

Results 241Am(n,f) 241Am(n,2n)240Am

Energy Production and Nuclear Waste Transmutation in ADS Systems Higher Fission/Capture ratio More effective Transmutation S. Taczanowski et. al. Applied Energy 75, 97, (2003) Sub-critical Systems Transmutation of Nuclear Waste Neutrons produced by Spallation Reaction in Accelerator Main Characteristics Neutron Flux in Reactor Core affected by n-induced reactions Minor Actinides (Am, Cm, Np) Not a good reactor fuel Not enough delayed neutrons

Off Line HPGe 241Am Target Pb shielding

Irradiation Setup D filled Gas Cell d+ n Beam 241Am Target Parafin 100000 200000 300000 400000 1000000 2000000 3000000 4000000 5000000 Neutron Flux (counts) Irradiation Time (sec) E n = 10.6 MeV Neutron Flux vs Time 5 days of Irradiation n Beam 241Am Target BF3 Neutron Counter

Mapping the Neutron beam fluctuations 100000 200000 300000 400000 1000000 2000000 3000000 4000000 5000000 Neutron Flux (counts) Irradiation Time (sec) E n = 10.6 MeV Neutron Flux vs Time 5 days of Irradiation

HPGe Pb

Measurement of the 241Am(n,2n) cross section by the activation method Experimental Difficulties Highly radioactive target, Relatively long half life of 240Am (50.8 h)