1. Name of Experiment:
 ------------------
 TUD Iron Slab Benchmark Experiment

2. Purpose and Phenomena Tested:
 ----------------------------
 Determination of spectral neutron flux, spectral photon flux and neutron
 time-of-arrival (TOA) flux penetrating and leaking iron slab assemblies
 (thickness: 30 cm; solid and with gap) irradiated with 14 MeV neutrons.

3. Description of Source and Experimental Configuration:
 ----------------------------------------------------
 The neutron source was a 14 MeV d-T neutron generator operated in pulsed
 mode. The time distribution of the source neutrons was proportional to
 exp[-(t/1.4 ns)**2]. The angular dependence of the source intensity is
 presented in Fig. 1. The angular dependence of the source energy
 distribution is shown in Fig. 2.
 The Fe slabs had a front area of 100 cm x 100 cm and a thickness of 30 cm
 and were built up by bricks with dimensions of 20 cm x 10 cm x 5 cm.
 Three assemblies were built up (see Figs. 3 and 4):
 A0 - no gap,
 A1 - vertical gap, distance: 10 cm from the centre, gap width: 5 cm, and
 A2 - vertical gap, distance: 20 cm from the centre, gap width: 5 cm.
 The distance between neutron source and Fe slab was 19 cm. The distance
 between Fe slab and detector was 300 cm. The distance between neutron
 source and detector was 349 cm.
 The angle between the d-beam of the neutron generator and an axis
 crossing neutron source and centre of the slab was 74 degrees.
 The detectors were positioned in a collimator shaped in such a way that
 all neutrons and photons leaking from the slab in direction of the
 detector could be observed.

4. Measurement System:
 ------------------
 A NE213 scintillator was employed for simultaneously measuring the
 spectral neutron flux, the spectral photon flux, and the neutron time-
 of-arrival spectrum for neutron energies of E > 1 MeV and photon energies
 of E > 0.2 MeV. For each registered event the pulse-height, the
 time-of-arrival, and a pulse-shape parameter were recorded to distinguish
 between neutrons and photons. [1-5]
 Pulse-height distributions from three different hydrogen-filled
 proportional detectors and a stilbene scintillator were used for
 determining the neutron flux spectra for energies ranging from 30 keV
 up to about 2.3 MeV, overlapping with the NE213 spectra.

5. Description of Results and Analysis:
 -----------------------------------
 Neutron energy spectrum:
 The NE213 pulse-height spectra were unfolded by the DIFBAS code [6] with
 a response matrix developed at Physikalisch-Technische Bundesanstalt
 Braunschweig [7], to obtain spectral fluxes.
 The evaluation procedure of the proton recoil spectra from the
 proportional detectors and from the stilbene scintillator consisted in an
 iterative differentiation with inclusion of corrections (wall effect,
 non-linear light output function, anisotropy effect of stilbene, energy
 dependent sensitivity of the stilbene crystal, correction of neutron
 reactions on carbon resulting in alpha-particles). The results are shown
 in Fig. 5.

 Neutron time-of-arrival spectrum:
 The neutron time-of-arrival distributions after the start pulse of the
 14 MeV source neutrons (t=0), recorded by the NE213 scintillation
 detector, are presented vs. calibrated time scale (Fig. 6). They are
 neither evaluated (e.g. with the detector efficiency (Fig. 8)) nor
 corrected.

 Photon energy spectrum:
 Photons produced by neutrons in the Fe assembly arrive at the detector
 in the time range between 10 ns and 50 ns; whereas those photons produced
 by neutrons in the walls and floor of the experimental hall, in the
 detector collimator, and in the detector itself, arrive later.
 Therefore, the pulse-height distribution from the NE213 detector for
 photons was taken only in this time-window and was unfolded with the
 DIFBAS code [6] with a response matrix from Physikalisch-Technische
 Bundesanstalt Braunschweig [8]. The results are shown in Fig. 7.

 Calculations:
 Examples of calculations carried out with the 3-D Monte Carlo code
 MCNP-4A [9] and the data libraries FENDL-1 [10] and EFF-2 [11] are
 presented (Figs. 9, 10, 11) [12].
 The geometry model for MCNP-4A including neutron source backing and the
 experimental environment (walls, floor, racks, ...) is given by the
 input file.

6. Quality assessment:
 ------------------
 The TUD IRON SLAB experiment is ranked as benchmark quality experiment. 
 For detailed evaluation see document IJS-DP-10216 (April 2009) by A. Milocco.

7. Author/Organizer:
 ----------------
 Experiment and analysis:
 H. Freiesleben, W. Hansen, D. Richter, K. Seidel, S. Unholzer
 Technische Universitaet Dresden
 Institut fuer Kern- und Teilchenphysik
 D-01062 Dresden
 Germany

 U. Fischer, Y. Wu
 Forschungszentrum Karlsruhe
 Institut fuer Neutronenphysik und Reaktortechnik
 Postfach 3640
 D-76021 Karlsruhe
 Germany

 Compiler of data for Sinbad:
 K. Seidel
 Technische Universitaet Dresden
 Institut fuer Kern- und Teilchenphysik
 D-01062 Dresden
 Germany
 
 Quality assessment:
 A. Milocco
 Institut Jožef Stefan
 Jamova 39
 Ljubljana
 Slovenia

 Reviewer of compiled data:
 A. Avery,
 Performance and Safety Services Department,
 AEA Technology
 WINFRITH, Dorchester
 Dorset DT2 8DH
 UK


8. Availability:
 ------------
 Unrestricted

9. References:
 ----------
 [1] H. Freiesleben, W. Hansen, H. Klein, T. Novotny, D. Richter, R.
 Schwierz, K. Seidel, M. Tichy, S. Unholzer, Experimental results of
 an iron slab benchmark, Report Technische Universitaet Dresden,
 TUD-PHY-94/2, February 1995
 [2] H. Freiesleben, W. Hansen, D. Richter, K. Seidel, S. Unholzer,
 Experimental investigation of neutron and photon penetration and
 streaming through iron assemblies, Fusion Engineering and Design 28
 (1995) 545-550
 [3] H. Freiesleben, W. Hansen, D. Richter, K. Seidel, S. Unholzer,
 Shield Penetration Experiments, Report Technische Universitaet
 Dresden, Institut fuer Kern- und Teilchenphysik, TUD-IKTP-95/01,
 January 1995
 [4] H. Freiesleben, W. Hansen, D. Richter, K. Seidel, S. Unholzer,
 TUD experimental benchmarks of Fe nuclear data, Fusion Engineering
 and Design 37 (1997) 31-37
 [5] U. Fischer, H. Freiesleben, H. Klein, W. Mannhardt, D. Richter,
 D. Schmidt, K. Seidel, S. Tagesen, H. Tsige-Tamirat, S. Unholzer,
 H. Vonach, Y. Wu, Application of improved neutron cross-section data
 for Fe-56 to an integral fusion neutronics experiment, Int. Conf. on
 Nuclear Data for Science and Technology, Trieste (Italy), May 19-24,
 1997
 [6] M. Tichy, The DIFBAS Program - Description and User's Guide, Report
 PTB-7.2- 193-1, Braunschweig 1993
 [7] S. Guldbakke, H. Klein, A. Meister, J. Pulpan, U. Scheler, M. Tichy,
 S. Unholzer, Response Matrices of NE213 Scintillation Detectors for
 Neutrons, Reactor Dosimetry ASTM STP 1228, Ed. H. Farrar et al.,
 American Society for Testing Materials, Philadelphia, 1995, p. 310-322
 [8] L. Buermann, S. Ding, S. Guldbakke, S. Klein, H. Novotny, M. Tichy,
 Response of NE213 Liquid Scintillation Detectors to High-Energy
 Photons, Nucl. Instr. Methods A 332(1993)483
 [9] J. F. Briesmeister (Ed.), MCNP - A general Monte Carlo n-particle
 transport code, version 4A, Report, Los Alamos National Laboratory,
 LA-12625-M, November 1993
 [10] S. Ganesan and P. K. McLaughlin, FENDL/E - evaluated nuclear data
 library of neutron interaction cross-sections and photon production
 cross-sections and photon-atom interaction cross-sections for fusion
 applications, version 1.0, Report IAEA-NDS-128, Vienna, May 1994
 [11] J. Kopecky, H. Gruppelaar, H.A.J. Vanderkamp and D. Nierop,
 European Fusion File, Version-2, EFF-2, Final report on basic data
 files, Report, ECN-C-92-036, Petten, June 1992.
 [12] Y. Wu, Report FZKA-5953, Karlsruhe, 1997
 [13] A. Milocco, The Quality Assessment of the FNG/TUD Benchmark Experiments,
 IJS-DP-10216, April 2009



10. Data and Format:
 ---------------


 DETAILED FILE DESCRIPTIONS
 --------------------------
 Filename Size[bytes] Content
 ---------------- ----------- -------------
Filename          Size[bytes]    Content
 ---------------- ----------- -------------
 1 tufe-abs.htm   14.116      This information file
 2 tufe-exp.htm  103.319      Description of Experiment
 3 MCNP.DAT       11.833      3-D model for MCNP-4A calculations 
                              (high quality)
 4 FIG-1.TIF     167.358      Figure 1: Angular dependence of the source 
                              intensity (high quality)
 5 FIG-2.TIF     667.922      Figure 2: Angular dependence of the source energy 
                              distribution (high quality)
 6 FIG-3.TIF     167.358      Figure 3: Geometries A0, A1, and A2 (horizontal section) 
                              (high quality)
 7 FIG-4.TIF     167.358      Figure 4: Geometries A0, A1, and A2 (vertical section) 
                              (high quality)
 8 FIG-5.TIF     667.922      Figure 5: Neutron spectra (high quality)
 9 FIG-6.TIF     667.922      Figure 6: Neutron time of arrival spectra (high quality)
10 FIG-7.TIF     667.922      Figure 7: Photon spectra (high quality)
11 FIG-8.TIF     167.358      Figure 8: Neutron detector efficiency of the NE213 detector
                              (high quality)
12 FIG-9.TIF     667.922      Figure 9: Neutron spectra for A0 geometry (experiment/MCNP) 
                              (high quality)
13 FIG-10.TIF    667.922      Figure 10: Neutron time of arrival spectra for A0 geometry 
                              (experiment/MCNP) (high quality)
14 FIG-11.TIF    667.922      Figure 11: Photon spectra for A0 geometry (experiment/MCNP) 
                              (high quality)
15 FIG-1.gif       6.045      Figure 1: Angular dependence of the source intensity (preview)
16 FIG-2.gif      16.521      Figure 2: Angular dependence of the source energy distribution 
                              (preview)
17 FIG-3.gif       7.544      Figure 3: Geometries A0, A1, and A2 (horizontal section) (preview)
18 FIG-4.gif       4.197      Figure 4: Geometries A0, A1, and A2 (vertical section) (preview)
19 FIG-5.gif      12.805      Figure 5: Neutron spectra (preview)
20 FIG-6.gif      11.877      Figure 6: Neutron time of arrival spectra (preview)
21 FIG-7.gif      12.271      Figure 7: Photon spectra (preview)
22 FIG-8.gif       7.397      Figure 8: Neutron detector efficiency of the NE213 detector 
                              (preview)
23 FIG-9.gif      13.889      Figure 9: Neutron spectra for A0 geometry (experiment/MCNP) 
                              (preview)
24 FIG-10.gif     11.414      Figure 10: Neutron time of arrival spectra for A0 geometry 
                              (experiment/MCNP) (preview)
25 FIG-11.gif     11.094      Figure 11: Photon spectra for A0 geometry (experiment/MCNP) 
                              (preview)
26 FNG-TUD.pdf   205,617      Document describing the quality assessment of FNG and TUD benchmarks

 File TUFE-EXP.HTM contains the following tables:

 1. Angular dependence of the source intensity
 (Relative intensity vs. COS(THETA))
 2. Angular dependence of the source energy distribution
 (Yield vs. energy for different COS(THETA))
 3. Chemical composition of iron
 4. Neutron detectors
 5. Neutron spectra for geometry A0 (Experiment)
 6. Neutron spectra for geometry A1 (Experiment)
 7. Neutron spectra for geometry A2 (Experiment)
 8. Neutron time-of-arrival spectra for geometry A0 (Experiment)
 9. Neutron time-of-arrival spectra for geometry A1 (Experiment)
 10. Neutron time-of-arrival spectra for geometry A2 (Experiment)
 11. Photon spectra for geometry A0 (Experiment)
 12. Photon spectra for geometry A1 (Experiment)
 13. Photon spectra for geometry A2 (Experiment)
 14. Neutron detection efficiency of the NE213 detector
 (Detection efficiency vs. energy, pointwise)
 15. Neutron spectra for geometry A0 (Calculation: FENDL-1, EFF-2)
 16. Neutron time-of-arrival spectra for geometry A0
 (Calculation: FENDL-1, EFF-2)
 17. Photon spectra for geometry A0 (Calculation: FENDL-1, EFF-2)

 The experimental data are provided in tabular form:
 Energy, spectrum, statistical uncertainty (one standard deviation),
 systematic uncertainty.
 The calculated data (MCNP) are provided in tabular form:
 Energy, spectrum calculated with FENDL-1, spectrum calculated with EFF-2.

 The figures describing the geometry of the experiment and the results are
 included in digitized page image form (TIFF format)and GIF (preview) format.
 
 
SINBAD Benchmark Generation Date: 8/1998
SINBAD Benchmark Last Update: 2/2010