Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom Status of Neutronics Tools & Data for IFMIF-EVEDA U. Fischer, S. Simakov Association FZK-Euratom Forschungszentrum Karlsruhe Germany Design Review Meeting IFMIF-EVEDA Test Facilities, Forschungszentrum Karlsruhe, March 26-27, 2007

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 Dedicated computational tools and data required: –D-Li neutron source term simulation –Neutron/photon transport calculations (E n > 20 MeV) –Activation and transmutation calculations (E n > 20 MeV) –Shielding calculations IFMIF Neutronics

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 D-Li Neutron Source Term

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 Enhancement to MCNP with ability to sample the generation of d- Li source neutrons on the basis of tabulated double-differential d + 6,7 Li cross-sections -Modelling of deuteron beam configuration, orientation and profile -Use of evaluated d+ 6,7 Li data to sample source neutrons -d + 6,7 Li cross-sections for deuteron energies up to 50 MeV ( A. Konobeyev et al, NSE 139 (2001)) -Updated evaluation (new methodology, P. Pereslavtsev, 2005) -McDeLicious standard code for IFMIF neutronics calculations Monte Carlo Code McDeLicious Developed to enable a proper representation of the d-Li neutron source term in Monte Carlo transport calculations for IFMIF D-Li Neutron Source Term

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 New d + 6,7 Li Data Evaluation P. Pereslavtsev et al, 2005 Neutron emission spectra in forward direction

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 McDeLicious validation analyses: Thick Li-target neutron forward yields as function of deuteron incidence energy

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 Neutron Cross-Section Data (E> 20 MeV) - General Purpose Data Files -

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 IFMIF project – 1 H, 56 Fe, 23 Na, 39 K, 28 Si, 12 C, 52 Cr, 51 V, 6,7 Li, 9 Be (INPE/FZK) - 180, ,186 W, 181 Ta (EFF/JEFF) LANL 150 MeV data files (ENDF/B-VI.6) - 1,2 H, 12 C, 16 O, 14 N, 27 Al, 28,29,30 Si, 31 P, 40 Ca, 50,52,53,54 Cr, 54,56,57,58 Fe, 58,60,61,62,64 Ni, 63,65 Cu, 93 Nb, 182,183,184,186 W, 196,198, 199, 200, 201, 202, 204 Hg, 206, 20, 208 Pb, 209 Bi NRG evaluations – 40,42-44,46,48 Ca, 45 Sc, Ti, 54,56-,58 Fe, 70,72-74,76 Ge, 204, Pb, 209 Bi JENDL-HE data file – 1 H, 12,13 C, 14 N, 16 O, Mg, 27 Al, Si, 39,41 K, 40,42- 46,48 Ca, Ti, 51 V, 50,52-54 Cr, 55 Mn, 54,56-58 Fe, 59 Co, 58,60-62,64 Ni, 63,65 Cu, 64,66- 68,70 Zn, ,94,96 Zr, 93 Nb, 180, ,186 W, 196, ,204 Hg Few other evaluations –KAERI ( 12 C, 27 Al, 56 Fe, 208 Pb), BNL ( 12 C, 56 Fe, 208 Pb, 209 Bi), IPPE ( U, 237,239 Np, Pu) Neutron Cross-Sections E  20 MeV - General purpose data ENDF evaluations -

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 Iron Transmission Benchmark Experiment (Shin et al.) Fe slabs (20, cm) irradiated with source neutrons produced by 65 MeV protons on Cu target Fe(nat) total neutron cross-section

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 Activation and Transmutation - Tools & Data -

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 Intermediate Energy Activation File IEAF-2001 (FZK/INPE) –Complete cross-section data library for activation and transmutation analyses up to E n  150 MeV (1  Z  84) –Uses lumped MT=5 reaction cross-sections with production yield vectors (LAW=0) on MF=6 file –Validated through series of benchmark calculations, tested and qualified for SS-316 & V/V-alloy samples in IFMIF activation experiments  Can be used with ALARA activation code (P. Wilson, UW) –Analytical and Laplacian Adaptive Radioactivity Analysis –Capable of handling an arbitrary number of reaction channels Activation and Transmutation - Tools and Data -

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 European Activation File EAF-2005 (UKAEA) –EAF data library extended to 60 MeV (based on TALYS + SAFEPAQ) –EAF data format using non-standard MT-numbers –Can be used with FISPACT-2005 inventory code (EASY system, UKAEA) –62,637 reactions from 50 data sources, 86 different reaction types –Extended decay data library with 2,192 nuclides EAF-2007: deuteron induced reactions –66,864 reactions from different sources, mostly TALYS ( –New calculated data library produced by TALYS for data using global parameters, included long-lived isomers as targets –New calculations using TALYS with local parameters produced by M. Avrigeanu for 27 Al, 54,56,57,58 Fe and 63,65 Cu (<50 MeV) EAF-2007: proton induced reactions –67,925 reactions, only based on data from TALYS calculations (so far)  FISPACT-2007 modified to handle d and p as incoming particle

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 NPI Rez Activation Experiments MCNPX model D 2 O Target (Ø30×26 mm 2 ) Activation Foils 1.7 mm47 mm ≈ 700 cm Neutron Detector 37 MeV protons C/E ratios of  –radio- activities induced in W p-D 2 O neutron spectrum

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 Neutron Spectrum Unfolding Technique μA proton beam -Heavy water target -Dosimetry foils: Al, Ti, Fe, Co, Ni, Y, Nb, Lu, Au (Ø12 x mm) hours irradiation -γ-activities measured by HPGe detector at cooling 1 h to 100 day; -Guess spectrum: measured by NE213 detector and simulated by MCNPX. Use of modified SAND-II code with cross sections from EAF-2005 Tested at the NPI cyclotron in neutron spectrum extending up to 35 MeV.

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 Gas production cross-sections

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 Radiation Shielding

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 Dedicated approach for coupled 3D Monte Carlo and deterministic (S N ) transport calculations for IFMIF shielding analyses Monte Carlo technique used to simulate the particle generation and transport in and around the neutron source region Discrete ordinates ( S N ) method used to treat the deep penetration problem in bulk shield. Mapping approach for calculating S N angular fluxes from scored data of Monte Carlo particle tracks crossing a specified surface Implemented in interface programme linking MCNP/McDeLicious and 3D S N code TORT of DOORS3.2 package Radiation Shielding

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, D shielding calculations for IFMIF Test Cell Dose rate distribution in access room Geometry model

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 McCad Model Generation

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 CAD Interface Programme McCAD Automatic conversion of CAD geometry data into semi-algebraic geometry representation for the MCNP Monte Carlo code -CAD data are imported via data files in neutral format (IGES, STEP) -Graphical User Interface (GUI) with components for modelling, visualization, and data exchange -McCAD is able to perform the conversion of the CAD data into MCNP geometry including the generation of voids and error analyses and repair (generation of full MCNP input deck) -McCAD can also generate CAD geometry models from available input decks (e. g. for visualization) -Successful test applications to JET and ITER (benchmarking)

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 Test Cell Model Converted by McCAD 2D cuts generated by MCNP geometry plotter Vertical cut of test cell Horizontal cut at target mid-plane level

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom U. Fischer, S. Simakov, Status Neutronics Tools & Data IFMIF Test Facility Review Meeting, FZK, March 26-27, 2007 Summary Codes for IFMIF neutronics –Transport: McDeLicious, MC/TORT, (MCNPX) –Geometry preparation: CAD/McCAD –Activation/transmutation: ALARA, FISPACT  Need to be further developed, in particular: McDeLicious, MC/TORT, McCAD Nuclear Data for IFMIF neutronics –Transport calculations: different sources, urgent need for qualified IFMIF reference data library (IAEA) –Activation/transmutation: IEAF-2001, EAF-2005/07 (n, p, d), to be further developed, improved and validated –Validation experiments, to be extended/continued –To be newly developed: dosimetry data file (extended IRDF)