Presentation on theme: "IAEA CRP on “Nuclear Data Libraries for Advanced Systems: Fusion Devices (FENDL-3)”- Contributions by FZK U. Fischer, A. Konobeyev, P. Pereslavtsev, S."— Presentation transcript:
1 IAEA CRP on “Nuclear Data Libraries for Advanced Systems: Fusion Devices (FENDL-3)”- Contributions by FZKU. Fischer, A. Konobeyev, P. Pereslavtsev, S. P. SimakovAssociation FZK-EuratomKarlsruhe Institute of TechnologyForschungszentrum Karlsruhe1st Research Coordination Meeting on “Nuclear Data Libraries for Advanced Systems – Fusion Devices (FENDL)”, IAEA, Vienna, December 2-5, 2008
2 OverviewRecent FZK activities related to fusion and high energy nuclear dataProposed CRP contributions by FZKData evaluationsData filesValidation analyses
3 Nuclear Data Evaluations for Fusion Technology and High Energy Applications Objectives:To provide cross-section data evaluations required for fusion neutronics calculations (transport and transmutation/activation)Evaluation of neutron induced cross-sections for EFF/JEFF (Joint Evaluated Fusion Fission File) up to 150 MeV neutron energyProduction of complete data files (ENDF6 data format) for processing with NJOY (use with MC & SN codes)Suitable for fusion and other applicationsComplete data files for 182,183,184,186W, 181Ta, 55Mn, 52Cr evaluationLargely with co-variance dataContributions to FENDL-3 project co-ordinated by IAEA/NDSEvaluation of d + 6,7Li data up to 50 MeV for IFMIF D-Li source term simulation using McDeLicious MC code
4 Flowchart of the evaluation procedure RIPL-2ECISTransmission coefficientsel, non, totNuclear model parametersMass tableNuclear level structureINPUT filesCollective excitationsENDF/B, JEFF-3.1, EAF2007GNASHEvaluated fileExperiment
5 Photon emission energy [MeV] Evaluation of n + 52Cr cross-section data up to 150 MeV for the Joint European Fusion Fission File (JEFF)Photon emission energy [MeV]
6 Evaluation of n + 181Ta cross-section data up to 150 MeV for the Joint European Fusion Fission File (JEFF)
7 Evaluation of n + 55Mn cross-section data up to 150 MeV for the Joint European Fusion Fission File (JEFF)
9 Benchmark analyses Objectives: To check and validate the new data evaluations for a reliable use in application calculations (ITER TBM, Demo, IFMIF) and provide feed-back to the evaluators.Computational analyses of integral benchmark experiments (14 MeV neutrons) by means of Monte Carlo calculations with the MCNP codeComparisons for neutron and photon spectra and other measured responses (e. g. reaction rates)Cross-checks with calculations using data evaluations from different sources (JEFF-3.0/3.1, FENDL-2.0/2.1, JENDL-3.3, ENDF/B-VI/VIIChecks of neutron emission cross-section data
10 Benchmark analyses on Ta Integral benchmark experimentsLawrence Livermore National Laboratory (LLNL) pulsed sphere experiments with central 14 MeV neutron source: Time-of-flight spectra for spherical Ta shells (wall thicknesses of 3.4 and 10.2 cm).Lewis Research Centre (LRC) experiment on 9 cm thick Ta shell with central Am-Be neutron source: Neutron leakage spectrum measurement by proton recoil scintillation detector.Differential experimental dataFew measurements of secondary neutron energy/angular distributions for incident energies 5 to 20 MeV by IPPE (Obninsk), IRK (Vienna), OSA (Osaka), TOH (Tohoku), TUD (Dresden)Available data evaluationsENDF/B-V (VI, VII), JENDL-3.3 (FENDL-2.1, JEFF-3.1), FZK 2006 (JEFF- 3.2)
11 Ta benchmark experiments Livermore (1986):Lewis Research Center (1974):Shell #1: outer R = cm (1 mfp)Shell #2: outer R = 10.2 cm (3 mfp)14 MeV-neutron source: TiT +d, Ed = 400 keVMethod: Time-of-Flight, L = 10 mn-detector: Θ = 26o, Ethresh > 1 MeVShell: outer R = cminner r = cm (wall 9 cm, 4 mfp)241Am-Be neutron source, <E> = 4 MeVMethod: Proton-recoil scintil. at L = 2 mn-detector: Θ = 26o, Ethresh > 1 MeVTa shellAm-Be sourcen-detectorL = 2 mL = 10 mΘ = 26od-beamn-detectorTa-ShellTiT-Target:14 MeV-SourceR
12 Benchmarking of Ta data LRC Ta shell experiment with Am-Be source (4 MeV mean neutron energy)LLNL Ta spheres experiments (14 MeV neutron source)
13 Benchmarking of Ta data Ta(n,xn) single and double differential neutron emission distributionsEin=7.94 MeVEin=14.1 MeVEin=7.94 MeV
14 Benchmarking of Ta data Ta(n,xn) single and double differential neutron emission distributionsEin=5.19 MeV
15 Benchmark analyses on Mn Integral neutron transport benchmark experiment:OKTAVIAN pulsed Mn sphere (dia. 61 cm) with central 14 MeV neutron source:n-leakage spectrum measured by Time-of-flight techniqueg-leakage spectrum measured by pulse height technique (NaI detector)Integral neutron activation benchmark experiment:JAERI/USDOE experiment with Mn-Cu alloy foil in quasi-mono energetic 14 MeV neutron source:3 radioactive isotopes were detected - Mn-54, Mn-56, V-52Differential experimental dataTwo measurements of secondary neutron energy/angular distributions at incident energy 14 MeV by TOH (Tohoku) and OKTAVIANAvailable data evaluationsENDF/B-VII and VII, JENDL-3.3 (adopted in FENDL-2.1 and JEFF-3.1) and FZK 2006 (JEFF-3.2)
16 Benchmarking of Mn data OKTAVIAN benchmark experiment- Mn spherical shell, R = cm (3.4 mfp for 14 MeV neutrons)- 14 MeV-neutron source: TiT +d, Ed = 240 keV- n-spectrometry: Time-of-Flight, NE218-detector at 11 m/55o, E = MeV- -spectrometry: Pulse-height/unfolding, NaI-detector at 5.8 m/55o, E = MeVL = 11 mΘ = 55od-beamγ-detectorNaI( pulse height)Mn shellTiT-Target:14 MeV-SourceRn-detectorNE-218(TOF)L = 5.8 m
17 Benchmarking of Mn data OKTAVIAN benchmark experiment: neutron leakage spectrumMn(n,xn) neutron emission spectra at 14 MeV incident neutron energy
18 Benchmarking of Mn data OKTAVIAN benchmark experiment: photon leakage spectrumMn(n,xg) neutron emission spectra at 14 MeV incident neutron energy
19 ITER Streaming Experiment at FNG Measurements of neutron/photon flux spectra by TUD (K. Seidel et al.)Mock-up of ITER inboard blanket/shield system with streaming channel in the blanket and cavity at the bottom of channel.Neutron and photon flux spectra measured at positions A (41.4 cm) and B (87.6 cm) with source on and off axis (A0, B0).Additional measurements with detectors shifted off the axis by 7.5 cm, 15.0 and 9.0 cm (A1, A2 and B1).Neutron spectra measured in the energy range between about 20 keV and 15 MeV.A set of gas-filled proportional counters and a stilbene scintillation spectrometer used in the energy range up to 3 MeV.NE-213 scintillation spectrometer for energy range 1 to 15 MeV.Photon flux spectra measured with NE-213 spectrometer above 0.2 MeV.Position A41.4 cmPosition B87.6 cm
20 ITER Streaming Experiment Neutron flux spectra at position B0
21 ITER Streaming Experiment Photon flux spectra at position B0
22 ITER Streaming Experiment Photon flux spectra at position B1
23 ITER Streaming Experiment C/E comparison for neutron flux integrals
24 ITER Streaming Experiment C/E comparison for photon flux integrals
25 Neutron Leakage Spectra from Pb-shells at 14 MeV incident neutron energy TUD shell (t = 22.5 cm)IPPE & IRD shell (t = 7.5 cm)
26 Secondary neutron Energy Distributions (SED) from Pb(n,xn) reaction at 14 MeV incident neutron energyNeutron emission for natural LeadNeutron emission and inelastic for Lead-208Findings: satisfactory agreement for energy differential cross sectionfor natPb(n,xn) and 208Pb(n,xn) or 208Pb(n,n’g) reactions at 14MeV
27 Gamma leakage spectra from Pb spherical shell & γ-spectra from Pb(n,xγ) reaction at 14 MeV incident neutron energyγ - Leakage Spectrum from Pb-Shellγ - Spectrum from Pb(n,xγ) reaction
28 Evaluation and validation of high energy cross-section data for the FENDL-3 nuclear data library Proposed research activities by FZKFull evaluations of neutron and proton induced high energy cross-section data (up to 150 MeV) including co-variance informationPreparation of data files in ENDF-6 formatValidation analyses based on Monte Carlo calculations of available integral experimentsPreparation of special radiation damage cross-sections for structural materials.
29 Proposed research activities by FZK Validation analysesMonte Carlo calculations with the MCNP code will be performed for the FENDL-3 data evaluations using suitable integral benchmark experiments.Measured and calculated responses will be compared and possible discrepancies will be analysed to identify deficient cross-section data.This information will be used to improve the FENDL-3 data evaluations.
30 Proposed research activities by FZK Neutron cross-section dataConsistent evaluation of high energy neutron cross-sections (up to 150 MeV) for selected nuclides such as Cr-50, -52, -53, -54, Mn-55, Ta-181, W-182, -183, -184, -186 and others including co-variance data information.General purpose 150 MeV data files will be prepared in standard ENDF-6 data and made available for FENDL-3.Proton activation cross-section dataCurrent version of the Proton Activation Data File PADF (comprising 418,575 excitation functions for 2355 target nuclei from Mg to Ra for proton energies from 0 up to 150 MeV) will be extended to include more nuclides, it will be updated to take into account new experiments, and will be complemented by co-variance data
31 Proposed research activities by FZK Radiation damage data:Neutron and proton induced displacement cross-section data will be evaluated for structural materials such as Cr, Fe, Ni and others using experimental information about defect generations in irradiated materials, results of molecular dynamics simulations, and results of binary collision approximation model calculations.These data will be prepared in a special data file for FENDL-3.
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