IAEA CRP on “Nuclear Data Libraries for Advanced Systems: Fusion Devices (FENDL-3)”- Contributions by FZK U. Fischer, A. Konobeyev, P. Pereslavtsev, S. P. Simakov Association FZK-Euratom Karlsruhe Institute of Technology Forschungszentrum Karlsruhe 1st Research Coordination Meeting on “Nuclear Data Libraries for Advanced Systems – Fusion Devices (FENDL)”, IAEA, Vienna, December 2-5, 2008

Overview Recent FZK activities related to fusion and high energy nuclear data Proposed CRP contributions by FZK Data evaluations Data files Validation analyses

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 energy Production of complete data files (ENDF6 data format) for processing with NJOY (use with MC & SN codes) Suitable for fusion and other applications Complete data files for 182,183,184,186W, 181Ta, 55Mn, 52Cr evaluation Largely with co-variance data Contributions to FENDL-3 project co-ordinated by IAEA/NDS Evaluation of d + 6,7Li data up to 50 MeV for IFMIF D-Li source term simulation using McDeLicious MC code

Flowchart of the evaluation procedure RIPL-2 ECIS Transmission coefficients el, non, tot Nuclear model parameters Mass table Nuclear level structure INPUT files Collective excitations ENDF/B, JEFF-3.1, EAF2007 GNASH Evaluated file Experiment

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]

Evaluation of n + 181Ta cross-section data up to 150 MeV for the Joint European Fusion Fission File (JEFF)

Evaluation of n + 55Mn cross-section data up to 150 MeV for the Joint European Fusion Fission File (JEFF)

Typical content of ENDF data files MF=1 General description. MT=451 MF=2 Resonance parameters. MT=151 MF=3 MT=1, 2, 4, 5, 16, 22, 28, 51-60, 91, 102,103, 104, 105, 106, 107 MF=4 Angular distributions. MT=2, 51-60 (Legendre polynomials) MF=6 Energy-angular distributions. MT=16,22,28,91, 103-107 (below 20 MeV), MT=5 (above 20 MeV): particles, photons, recoils MF=12 Photon production multiplicities and transmission probabilities. MT=16,22,28,51-60,91,102-107 MF=14 Photon angular distributions. MT=16,22,28,51-60,91,102-107 MF=15 Photon energy spectra. MT=16,22,28,91,102-107

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 code Comparisons 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/VII Checks of neutron emission cross-section data

Benchmark analyses on Ta Integral benchmark experiments Lawrence 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 data Few 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 evaluations ENDF/B-V (VI, VII), JENDL-3.3 (FENDL-2.1, JEFF-3.1), FZK 2006 (JEFF- 3.2)

Ta benchmark experiments Livermore (1986): Lewis Research Center (1974): Shell #1: outer R = 3.4 cm (1 mfp) Shell #2: outer R = 10.2 cm (3 mfp) 14 MeV-neutron source: TiT +d, Ed = 400 keV Method: Time-of-Flight, L = 10 m n-detector: Θ = 26o, Ethresh > 1 MeV Shell: outer R = 12.1 cm inner r = 3.1 cm (wall 9 cm, 4 mfp) 241Am-Be neutron source, <E> = 4 MeV Method: Proton-recoil scintil. at L = 2 m n-detector: Θ = 26o, Ethresh > 1 MeV Ta shell Am-Be source n-detector L = 2 m L = 10 m Θ = 26o d-beam n-detector Ta-Shell TiT-Target: 14 MeV-Source R

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)

Benchmarking of Ta data Ta(n,xn) single and double differential neutron emission distributions Ein=7.94 MeV Ein=14.1 MeV Ein=7.94 MeV

Benchmarking of Ta data Ta(n,xn) single and double differential neutron emission distributions Ein=5.19 MeV

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 technique g-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-52 Differential experimental data Two measurements of secondary neutron energy/angular distributions at incident energy 14 MeV by TOH (Tohoku) and OKTAVIAN Available data evaluations ENDF/B-VII and VII, JENDL-3.3 (adopted in FENDL-2.1 and JEFF-3.1) and FZK 2006 (JEFF-3.2)

Benchmarking of Mn data OKTAVIAN benchmark experiment - Mn spherical shell, R = 30.5 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 = 0.076 -14 MeV -  -spectrometry: Pulse-height/unfolding, NaI-detector at 5.8 m/55o, E = 0.5-11 MeV L = 11 m Θ = 55o d-beam γ-detector NaI( pulse height) Mn shell TiT-Target: 14 MeV-Source R n-detector NE-218(TOF) L = 5.8 m

Benchmarking of Mn data OKTAVIAN benchmark experiment: neutron leakage spectrum Mn(n,xn) neutron emission spectra at 14 MeV incident neutron energy

Benchmarking of Mn data OKTAVIAN benchmark experiment: photon leakage spectrum Mn(n,xg) neutron emission spectra at 14 MeV incident neutron energy

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 A 41.4 cm Position B 87.6 cm

ITER Streaming Experiment Neutron flux spectra at position B0

ITER Streaming Experiment Photon flux spectra at position B0

ITER Streaming Experiment Photon flux spectra at position B1

ITER Streaming Experiment C/E comparison for neutron flux integrals

ITER Streaming Experiment C/E comparison for photon flux integrals

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)

Secondary neutron Energy Distributions (SED) from Pb(n,xn) reaction at 14 MeV incident neutron energy Neutron emission for natural Lead Neutron emission and inelastic for Lead-208 Findings: satisfactory agreement for energy differential cross section for natPb(n,xn) and 208Pb(n,xn) or 208Pb(n,n’g) reactions at 14MeV

Gamma leakage spectra from Pb spherical shell & γ-spectra from Pb(n,xγ) reaction at 14 MeV incident neutron energy γ - Leakage Spectrum from Pb-Shell γ - Spectrum from Pb(n,xγ) reaction

Evaluation and validation of high energy cross-section data for the FENDL-3 nuclear data library Proposed research activities by FZK Full evaluations of neutron and proton induced high energy cross-section data (up to 150 MeV) including co-variance information Preparation of data files in ENDF-6 format Validation analyses based on Monte Carlo calculations of available integral experiments Preparation of special radiation damage cross-sections for structural materials.

Proposed research activities by FZK Validation analyses Monte 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.

Proposed research activities by FZK Neutron cross-section data Consistent 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 data Current version of the Proton Activation Data File PADF-2007 (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

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.