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Neutronics and Nuclear Data for IFMIF - Overview -

Neutronics and Nuclear Data for IFMIF - Overview -. Ulrich Fischer Association FZK-Euratom Forschungszentrum Karlsruhe Y. Chen a) , S. P. Simakov b) , P.P.H. Wilson c) , P. Vladimirov b), F. Wasastjerna d).

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Neutronics and Nuclear Data for IFMIF - Overview -

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  1. Neutronics and Nuclear Data for IFMIF- Overview - Ulrich Fischer Association FZK-Euratom Forschungszentrum Karlsruhe Y. Chena), S. P. Simakovb), P.P.H. Wilsonc), P. Vladimirovb), F. Wasastjernad) a)ASIPP, Hefei, China; b) Forschungszentrum Karlsruhe, Germany; c)University of Wisconsin-Madison, USA; d) VTT Processes, Finland IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  2. PIE Facilities Access cell Test Cell 0 20 40m IFMIF Intense Neutron Source U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  3. Medium Flux Low Flux Deuteron Beam Liquid Li Jet High Flux Beam Spot (20x5cm2) IFMIF Intense Neutron Source • Deuteron beams: • 2 x 125 mA • Ed = 40 MeV • Neutron production: •  1.1  1017 s -1 • Test volumes: • high flux: 0.5 L > 20 dpa/fpy(*) • medium flux: 6 L > 1 dpa/fpy, • low flux: 7.5 L 0.1-1 dpa/fpy • (*)fpy = full power year U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  4. IFMIF neutron flux spectrum U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  5. IFMIF Neutronics Issues • Prove IFMIF’s suitability as neutron source for fusion-specific simulation irradiations • Provide reliable data for the technical layout of facility • Computational tools and data required • D-Li neutron source term simulation • Neutron transport (En> 20 MeV) • Activation and transmutation (En> 20 MeV) Key role of neutronics in establishing IFMIF as neutron source for fusion material testing U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  6. D-Li Neutron Source Term • D-Li source neutrons for MC transport simulation • D-Li interaction processes • Neutron yield & spectra (energy, angle) • To be integrated to standard MC code (MCNP) • MCNP  McDeLi (P. P. H. Wilson, 1998) • Semi-empirical reaction model with adjustable parameters • Deuteron beam configuration, orientation and profile • McDeLi  McDeLicious (S. P. Simakov, 2001) • Use of evaluated d+ 6,7Li data to sample source neutrons • d + 6,7Li cross-sections for deuteron energies up to 50 MeV (A. Konobeyev et al, NSE 139 (2001))  Improved new evaluation 2005 (P. Pereslavtsev, FZK) U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  7. Thick Li-target neutron yields Total (4π) Neutron Yields Forward (0o) Neutron Yields U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  8. D-Li thick target neutron yield spectra Ed= 25 MeV U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  9. D-Li thick target neutron yield spectra Ed= 40 MeV U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  10. Li(d,xn) Double Differential Cross Sections Ed = 17 MeV, Bem et al. Ed = 40 MeV, Baba et al. U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  11. New d + Li Data Evaluation  P. Pereslavtsev, this meeting U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  12. Thick Li-target neutron yields using 2005 D-Li data evaluation (P. Pereslavstev et al.) U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  13. IFMIF Test Cell Calculations • Major neutronics task in this context: • Provide the data required for the design and optimisation of the irradiation test modules and the lay-out of the test cell  Neutron/photon transport calculations (McDeLicious) for flux distributions and nuclear responses such as nuclear heating, radiation damage accumulation and gas production. • IFMIF’ s primary mission is to generate a materials irradiation database for the design, construction, licensing and operation of DEMO U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  14. Materials for IFMIF • Highest priority: structural materials of the reduced activation ferritic-martensitic (RAFM) type (Eurofer, F82H). • A variety of Eurofer specimens will be irradiated in the high flux test module (HFTM) up to the target fluence of 150 dpa. • Other materials of (possibly) lower priority: • SiC, V/V-alloy, divertor materials (e. g. W) • Breeder materials, neutron multiplier • Ceramic insulators and others U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  15. Chemical Composition of RAFM Steel Eurofer U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  16. Neutron Cross-Sections E  20 MeV - General purpose data ENDF evaluations - • IFMIF project (INPE Obninsk/FZK) • 1H, 56Fe,23Na, 39K, 28Si, 12C, 52Cr, 51V (50 MeV) • 6,7Li, 9Be (150 MeV) • LANL 150 MeV data files (ENDF/B-VI.6) • 1,2H, 12C, 16O, 14N, 27Al, 28,29,30Si, 31P, 40Ca, 50,52,53,54Cr, 54,56,57,58Fe, 58,60,61,62,64Ni, 63,65Cu, 93Nb, 182,183,184,186 W, 196,198, 199, 200, 201, 202, 204 Hg, 206, 20, 208 Pb, 209Bi • NRG evaluations • 40,42-44,46,48Ca- 45Sc, 46-50Ti, 54,56-,58Fe, 70,72-74,76Ge, 204,206-208Pb, 209Bi • JENDL-HE data file • 1H, 12,13C, 14N, 16O, 24-26Mg, 27Al, 28-30Si, 39,41K, 40,42- 46,48Ca, 46-50Ti,51V, 50,52-54Cr, 55Mn, 54,56-58Fe, 59Co, 58,60-62,64Ni, 63,65Cu, 64,66-68,70Zn,90- 92,94,96Zr, 93Nb, 180,182-184,186W, 196,198-202,204Hg  T. Fukahori, this meeting U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  17. Iron Transmission Benchmark Experiment (Shin et al.) Fe slabs (20, 40 50 cm) irradiated with source neutrons produced by 65 MeV protons on Cu target Fe(nat) total neutron cross-section U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  18. CAD model (CATIA) IFMIF Test Cell MCNP model (visualised by CATIA) Irradiation test modules Accelerator lines Li target U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  19. IFMIF High Flux Test Module (HFTM) HFTM container HFTM test rig vertical cut horizontal cut U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  20. Distributions of nuclear responses in the HFTM Displacement damage rate [dpa / fpy] Nuclear heating [ W/ cm3] McDeLicious calculations with simplified geometry model  S. P. Simakov, this meeting U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  21. Distributions of nuclear responses in HFTM test rigs HFTM Displacement damage Nuclear heating McDeLicious calculations with detailed 3D geometry model U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  22. IFMIF Medium Flux Test Module (MFTM) Creep- Fatigue Test Module (CFTM) Tritium Release Module (TRM) U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  23. LFTM Be rigs (TRM) W spectral shifter plate Creep-fatigue testing machine HFTM C neutron reflector Li target MFTM: MCNP geometry model (horizontal cut) U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  24. He vs. H-3 production rates in Be rigs of MFTM U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  25. W/g Nuclear Heating in Pulling Rods of CFTM  P. Vladimirov, this meeting U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  26. Activation and Transmutation Analyses • Intermediate Energy Activation File IEAF-2001 (FZK/INPE) • Complete cross-section data library for activation and transmutation analyses up to En 150 MeV (1  Z  84) • Validated through series of benchmark calculations, tested and qualified for SS-316 & V/V-alloy samples in IFMIF activation experiment • ALARA activation code (P. Wilson, UW) • Analytical and Laplacian Adaptive Radioactivity Analysis • Capable of handling an arbitrary number of reaction channels  EAF-2005 (En 60 MeV) for FISPACT inventory calculations recently became available (UKAEA Culham) Tools and Data  U. Fischer, this meeting  R. Forrest, this meeting U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  27. IEAF-2001 Validation Analyses Activation experiments in IFMIF-like white neutron field (U. v. Möllendorff et al., FZK; P. Bem et al. NPI Rez) Eurofer-97,SS-316, F82H, V alloy (FZK) Calculated (C) vs. measured (E) g-radioactivities Tungsten  S. P. Simakov, this meeting U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  28. Induced radioactivity in the IFMIF HFTM components IFMIF HTFM components (CAD model) Contact g - dose rate after IFMIF full power irradiation [Sv/h] U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  29. Elemental Transmutation of Eurofer in HFTM • Assessed by McDeLicious transport and ALARA/IEAF-2001 inventory calculations U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  30. He production cross-section of Fe-nat up to 100 MeV  B. Haight, this meeting U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  31. 3-D shielding analyses of IFMIF • Dedicated approach for coupled 3D Monte Carlo and deterministic (SN) 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 (SN) method used to treat the deep penetration problem in bulk shield. • Mapping approach for calculating SN angular fluxes from scored data of Monte Carlo particle tracks crossing a specified surface • Implemented in interface programme linking MCNP/McDeLicious and 3D SN code TORT of DOORS3.2 package U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  32. 3-D shielding calculations for IFMIF Test Cell Dose rate distribution in access room Geometry model U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  33. Conclusions • Suitable computational tools, data and models available for IFMIF neutronics and activation analyses • McDeLicious Monte Carlo code for Li(d,xn) neutron source generation and transport simulation. • MC transport simulation calculations (e. g. test cell): • Various general purpose intermediate/high energy data evaluations • Activation and transmutation calculations: • ALARA inventory code with IEAF-2001 data • FISPACT code with EAF-2005 • Coupled Monte Carlo – Discrete Ordinates (SN) computational scheme for full 3D shielding calculations • Detailed 3D geometry model of the entire IFMIF test cell. IFMIF neutronics and nuclear data: significant progress U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

  34. Outlook • D-Li neutron source term • d + 6.7Li evaluation to be validated • Further improvements required ? • General purpose (ENDF) data evaluations E> 20 MeV • Need for full IFMIF nuclear data library • Benchmark experiments/analyses required • Cross-section measurements • Activation/transmutation/gas production data • Need for validation ( Benchmark experiments) • Need for cross-section measurements • Deuteron induced activation cross-sections U. Fischer, IFMIF Neutronics & Nuclear Data IAEA TC Meeting, Karlsruhe, October 4-6, 2005

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