"README.DOC" BEGINS June 30, 1993 IAEA Benchmark Problem Based on the Lead Sphere Experiment at TU Dresden Collaboration IAE Moscow, ZfK Rossendorf and TU Dresden Contacts: K. SEIDEL, Institute of Nuclear and Particle Physics, Technical University of Dresden, Mommsenstr. 13, D-01062 Dresden, Germany Phone + Telefax: +49-3501-527544 1. Numerical Data and Their Format a) Type of format : IBM-PC, MS-DOS file in (3.5", 1.44MB) b) There are the following three files except this "README.DOC" text: PBTG.DAT ----- Source neutron spectrum PB.DAT ----- Neutron leakage spectrum ENERGY.DAT ----- Boundary energies c) Units of the data Source spectrum [n/lethargy/source neutron] Leakage spectrum [n/lethargy/source neutron] d) Data format of the experimental data Comment 1 line 20A4 Energy (mid-point) [MeV] I = 1, 43 6E12.4 Leakage spectrum I = 1, 43 6E12.4 Error (fraction) [%] I = 1, 43 6E12.4 e) Data format of the boundary energies (ENERGY.DAT) Comment 1 line 20A4 Boundary energy [MeV] I = 1, 44 8F9.5 2. Geometrical Arrangement (1) Neutron Source Isotropic point source of 3H(d,n)4He-neutrons in the centre of the spherical lead assembly. The energy distribution of the neutrons normalized to 1.0 is given in the file PBTG.DAT in the same group structure as the leakage spectrum. (2) Lead Sphere - Metallic Pb, chemical purity of 99.99% - Density : (11.35 ñ 0.10) g/cm**3 - Inner radius: 2.5 cm - Outer radius: 25 cm - Distance between target and detector : 431 cm 3. Additional Results Table 1: Neutron Leakage per Source Neutron (Partial and Total Neutron Multiplications of the Sphere) ------------------------------------------- Energy Interval Neutron Leakage Error E [MeV] [%] ------------------------------------------- 0.045...1.0 1.126 ñ 0.115 10.2 1.0...5.0 0.668 ñ 0.060 9.0 5.0...10.0 0.0204 ñ 0.0017 8.3 10.0...14.9 0.140 ñ 0.010 7.3 0.045...14.9 1.955 ñ 0.187 9.6 ------------------------------------------- Table 2: Activation and Fission Rates per Source Neutron and Nucleus ------------------------------------------------- Nuclide Reaction Rate at the Surface Error of the Sphere * [1/s] [%] ------------------------------------------------- 103-Rh (n,n') 1.34-28 # 16 ------------------------------------------------- 115-In (n,n') 2.46-29 16 ------------------------------------------------- 58-Ni (n,p) 1.69-29 17 ------------------------------------------------- 64-Zn (n,p) 7.79-30 17 ------------------------------------------------- 27-Al (n,alpha) 2.39-30 15 ------------------------------------------------- 203-Tl (n,2n) 3.12-29 16 ------------------------------------------------- 65-Cu (n,2n) 2.26-29 20 ------------------------------------------------- 235-U (n,f) 3.44-28 11.9 ------------------------------------------------- 238-U (n,f) 4.93-29 7.1 ------------------------------------------------- 237-Np (n,f) 2.56-28 8.2 ------------------------------------------------- 232-Th (n,f) 1.42-29 11.3 ------------------------------------------------- 239-Pu (n,f) 5.61-28 12.0 ------------------------------------------------- # Read as 1.34x10**(-28) * The fission rate detector was placed at a distance of 0.25 cm to the surface of the sphere, e.g. the total radius was 25.25 cm. 4. References When you publish the results using this numerical data, you should refer to reference 1). 1) T. Elfruth, D. Seeliger, K. Seidel, G. Streubel, S. Unholzer, D. Albert, W. Hansen, K. Noack, C. Reiche, W. Vogel, D.V. Markovskij and G.E. Shatalov: "The neutron multiplication of lead at 14 MeV neutron incidence energy", Atomkernenergie-Kerntechnik 49(1987) 121-125 2) K. Noack and D. Albert: "Determination of Neutron Background in Pb Sphere Leakage Spectrum Measurements by Means of MORSE Calculations", Kernenergie 30(1987)111-114 "README.DOC" ENDS "ENERGY.DAT" BEGINS Boundary energies for the experimental data in MeV 0.04500 0.05500 0.06500 0.07500 0.08500 0.09500 0.11000 0.13500 0.16500 0.19000 0.25000 0.35000 0.45000 0.55000 0.65000 0.75000 0.85000 0.95000 1.10000 1.35000 1.65000 1.90000 2.25000 2.75000 3.25000 3.75000 4.25000 4.75000 5.25000 5.75000 6.25000 6.75000 7.25000 7.75000 8.25000 8.75000 9.25000 9.75000 10.25000 10.75000 11.25000 11.75000 12.20000 14.90000 "ENERGY.DAT" ENDS "PB.DAT" BEGINS LEAD SPHERE, leakage spectrum 4.97494E-02 5.97913E-02 6.98212E-02 7.98436E-02 8.98610E-02 1.02225E-01 1.21861E-01 1.49248E-01 1.77059E-01 2.17945E-01 2.95804E-01 3.96863E-01 4.97494E-01 5.97913E-01 6.98212E-01 7.98436E-01 8.98610E-01 1.02225E+00 1.21861E+00 1.49248E+00 1.77059E+00 2.06761E+00 2.48747E+00 2.98957E+00 3.49106E+00 3.99218E+00 4.49305E+00 4.99375E+00 5.49432E+00 5.99479E+00 6.49519E+00 6.99553E+00 7.49583E+00 7.99609E+00 8.49632E+00 8.99653E+00 9.49671E+00 9.99687E+00 1.04970E+01 1.09972E+01 1.14973E+01 1.19729E+01 1.41000E+01 4.77732E-02 5.71038E-02 6.86467E-02 7.97594E-02 9.03474E-02 1.01433E-01 1.28227E-01 1.69017E-01 2.09862E-01 2.63597E-01 3.72729E-01 5.42458E-01 7.08543E-01 7.92941E-01 8.12722E-01 8.48926E-01 8.74187E-01 8.54362E-01 7.96690E-01 7.29777E-01 5.98334E-01 4.55843E-01 2.88635E-01 1.67495E-01 1.00492E-01 6.64893E-02 4.67122E-02 3.61992E-02 2.94101E-02 2.61406E-02 2.45010E-02 2.59298E-02 2.69863E-02 2.83401E-02 3.17577E-02 3.39530E-02 3.53512E-02 3.30260E-02 3.13704E-02 3.20436E-02 3.28789E-02 3.30000E-02 6.70000E-01 1.00000E+01 1.00000E+01 1.00000E+01 1.00000E+01 1.00000E+01 1.00000E+01 1.00000E+01 1.00000E+01 1.00000E+01 1.00000E+01 1.00000E+01 1.01000E+01 1.01000E+01 1.02000E+01 1.03000E+01 1.04000E+01 1.05000E+01 1.05000E+01 1.05000E+01 9.80000E+00 8.30000E+00 7.10000E+00 6.70000E+00 6.80000E+00 7.00000E+00 7.20000E+00 7.40000E+00 7.50000E+00 7.70000E+00 7.90000E+00 8.10000E+00 8.25000E+00 8.40000E+00 8.60000E+00 8.80000E+00 9.00000E+00 9.10000E+00 9.30000E+00 9.50000E+00 9.60000E+00 9.70000E+00 9.90000E+00 7.20000E+00 "PB.DAT" ENDS "PBTG.DAT" BEGINS Neutron Source Spectrum 4.97494E-02 5.97913E-02 6.98212E-02 7.98436E-02 8.98610E-02 1.02225E-01 1.21861E-01 1.49248E-01 1.77059E-01 2.17945E-01 2.95804E-01 3.96863E-01 4.97494E-01 5.97913E-01 6.98212E-01 7.98436E-01 8.98610E-01 1.02225E+00 1.21861E+00 1.49248E+00 1.77059E+00 2.06761E+00 2.48747E+00 2.98957E+00 3.49106E+00 3.99218E+00 4.49305E+00 4.99375E+00 5.49432E+00 5.99479E+00 6.49519E+00 6.99553E+00 7.49583E+00 7.99609E+00 8.49632E+00 8.99653E+00 9.49671E+00 9.99687E+00 1.04970E+01 1.09972E+01 1.14973E+01 1.19729E+01 1.41000E+01 6.05448E-04 6.94744E-04 8.04334E-04 9.16393E-04 1.04160E-03 2.10981E-03 2.98493E-03 3.59289E-03 4.22542E-03 5.52539E-03 7.58425E-03 9.52177E-03 1.13794E-02 1.27504E-02 1.38622E-02 1.48153E-02 1.52057E-02 1.46065E-02 1.61587E-02 1.70864E-02 1.72069E-02 1.73741E-02 1.84892E-02 1.89907E-02 1.84643E-02 1.72655E-02 1.55527E-02 1.41484E-02 1.29471E-02 1.40173E-02 1.50077E-02 1.49291E-02 1.41569E-02 1.20742E-02 1.14328E-02 1.12605E-02 9.90320E-03 1.01351E-02 1.09705E-02 1.42526E-02 1.69059E-02 2.43287E-02 4.70332E+00 1.32000E+00 1.35000E+00 1.36000E+00 1.36000E+00 1.36000E+00 8.30000E-01 5.90000E-01 5.50000E-01 6.00000E-01 3.80000E-01 3.00000E-01 3.10000E-01 3.10000E-01 3.20000E-01 3.40000E-01 3.50000E-01 3.60000E-01 3.20000E-01 2.60000E-01 2.50000E-01 3.00000E-01 2.70000E-01 2.40000E-01 2.60000E-01 2.80000E-01 3.10000E-01 3.50000E-01 3.90000E-01 4.20000E-01 4.20000E-01 4.30000E-01 4.40000E-01 4.70000E-01 5.30000E-01 5.70000E-01 5.90000E-01 6.50000E-01 6.60000E-01 6.50000E-01 5.70000E-01 5.40000E-01 4.80000E-01 1.50000E-04 "PBTG.DAT" ENDS