"README.DOC" BEGINS June 30, 1993 IAEA Benchmark Problem Based on the Uranium 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: UTG.DAT ------ Source neutron spectrum U.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, 48 6E12.4 Leakage spectrum I = 1, 48 6E12.4 Error (fraction) [%] I = 1, 48 6E12.4 e) Data format of the boundary energies (ENERGY.DAT) Comment 1 line 20A4 Boundary energies [MeV] I = 1, 49 8F9.5 2. Geometrical Arrangement (1) Neutron Source Isotropic point source of 3H(d,n)4He-neutrons in the centre of the spherical uranium assembly. The energy distribution of the neutrons normalized to 1.0 is given in the file UTG.DAT in the same group structure as the leakage spectrum. (2) Uranium Sphere The spherical assembly consists of metallic uranium depleted in U-235 to 0.4%. Basic data are as follows: Inner radius of assembly : 10 cm Outer radius of assembly : 16 cm Distance between target and detector : 451 cm 3. Additional Results Table 1: Neutron Leakage from the Sphere per one 14-MeV Source Neutron Energy Interval Neutron Leakage Error E [MeV] [%] ------------------------------------------- 0.12...1.0 1.305 ñ 0.127 9.7 1.0...5.0 0.511 ñ 0.037 7.2 5.0...10.0 0.043 ñ 0.002 5.4 10.0...15.0 0.438 ñ 0.028 6.4 0.12...15.0 2.297 ñ 0.194 8.4 0...15.0 2.459 ñ 0.213 8.7 * ------------------------------------------- * For E = 0...0.12 MeV the value 0.162 calculated with MORSE-ENDF/B-IV was added. Table 2: Activation and Fission Rates per Source Neutron and Nucleus [1/s] ----------------------------------------------------------------- Reaction Effective Rate at the Surface Rate without Threshold of the Sphere * Uranium Sphere * [MeV] [1/s] [1/s] ----------------------------------------------------------------- 65-Cu(n,2n) 12.4 1.26-28# 2.66-28 (20) (20) ----------------------------------------------------------------- 203-Tl(n,2n) 7.9 1.16-28 2.77-28 (20) (20) ----------------------------------------------------------------- 238-U (n,f) 1.5 2.625-28 3.596-28 (5) (5) ----------------------------------------------------------------- 232-Th(n,f) 1.4 6.674-29 7.527-29 (5) (5) ----------------------------------------------------------------- 237-Np(n,f) 0.6 1.240-27 6.364-28 (5) (5) ----------------------------------------------------------------- 235-U (n,f) --- 1.433-27 6.405-28 (5) (5) ----------------------------------------------------------------- # Read as 1.26x10**(-28), (error in %) * The activation rate measurements were carried out with probes of 20 mm diameter and 5 mm thickness. The fission rate detector (parallel plate fission chamber) was placed at a distance of 8 mm to the surface of the sphere, e.g. the total radius was 16.8 cm. For comparison with calculated results it is useful to normalize the activation rate and the fission rate at the surface of the sphere to the value obtained without uranium shell. In this case systematic errors will be decreased. 4. Reference When you publish the results using this numerical data, you should refer to T. Elfruth, T. Hehl, M. Toepfer, D. Seeliger, K. Seidel, G. Streubel, S. Unholzer, D. Albert, W. Hansen, Ch. Reiche, W. Vogel, A. Borisov, D. Markovskij and G. Shatalov: "The neutron leakage spectrum from a uranium sphere fed with 14-MeV neutrons", Kerntechnik 55(1990) 156-160 "README.DOC" ENDS "ENERGY.DAT" BEGINS Boundary energies for the experimental data in MeV 0.12277 0.13569 0.14996 0.16573 0.18316 0.20242 0.22371 0.24724 0.27324 0.30197 0.33373 0.36883 0.40762 0.45049 0.49787 0.55023 0.60810 0.67206 0.74274 0.82085 0.90718 1.00259 1.10803 1.22456 1.35335 1.49569 1.65299 1.82683 2.01896 2.23130 2.46597 2.72532 3.01194 3.32871 3.67879 4.06570 4.49329 4.96585 5.48812 6.06531 6.70320 7.40818 8.18731 9.04837 10.00000 11.05171 12.21403 13.49859 14.91824 "ENERGY.DAT" ENDS "U.DAT" BEGINS URANIUM SPHERE, leakage spectrum 1.29068E-01 1.42642E-01 1.57644E-01 1.74224E-01 1.92547E-01 2.12797E-01 2.35177E-01 2.59911E-01 2.87246E-01 3.17456E-01 3.50843E-01 3.87742E-01 4.28521E-01 4.73589E-01 5.23397E-01 5.78443E-01 6.39279E-01 7.06512E-01 7.80817E-01 8.62936E-01 9.53691E-01 1.05399E+00 1.16484E+00 1.28735E+00 1.42274E+00 1.57237E+00 1.73774E+00 1.92050E+00 2.12248E+00 2.34570E+00 2.59240E+00 2.86505E+00 3.16637E+00 3.49938E+00 3.86741E+00 4.27415E+00 4.72366E+00 5.22046E+00 5.76950E+00 6.37628E+00 7.04688E+00 7.78801E+00 8.60708E+00 9.51229E+00 1.05127E+01 1.16183E+01 1.28403E+01 1.41907E+01 2.97702E-01 3.25725E-01 3.63152E-01 4.00911E-01 4.35625E-01 4.79060E-01 5.23570E-01 5.65241E-01 6.08857E-01 6.59368E-01 6.82113E-01 6.91128E-01 7.29497E-01 7.85410E-01 8.39826E-01 8.61331E-01 8.26727E-01 8.10438E-01 7.85837E-01 7.36132E-01 6.63359E-01 5.83322E-01 5.41457E-01 4.95540E-01 4.45133E-01 3.94405E-01 3.75091E-01 3.39129E-01 3.14449E-01 2.86764E-01 2.60489E-01 2.38299E-01 2.13312E-01 1.79908E-01 1.56386E-01 1.40336E-01 1.22063E-01 9.55219E-02 7.83824E-02 6.29601E-02 5.54116E-02 4.99419E-02 4.65837E-02 4.61538E-02 4.73269E-02 6.43924E-02 1.80352E-01 4.08564E+00 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 1.00000E+01 1.00000E+01 1.00000E+01 9.90000E+00 9.70000E+00 9.50000E+00 9.30000E+00 9.10000E+00 8.90000E+00 8.60000E+00 8.40000E+00 8.20000E+00 8.00000E+00 7.90000E+00 7.70000E+00 7.45000E+00 7.20000E+00 7.00000E+00 6.80000E+00 6.50000E+00 6.15000E+00 5.80000E+00 5.40000E+00 5.00000E+00 4.60000E+00 4.30000E+00 4.30000E+00 4.70000E+00 5.30000E+00 5.80000E+00 6.10000E+00 6.50000E+00 6.60000E+00 6.60000E+00 6.50000E+00 6.50000E+00 6.40000E+00 "U.DAT" ENDS "UTG.DAT" BEGINS Neutron Source Spectrum 1.29068E-01 1.42642E-01 1.57644E-01 1.74224E-01 1.92547E-01 2.12797E-01 2.35177E-01 2.59911E-01 2.87246E-01 3.17456E-01 3.50843E-01 3.87742E-01 4.28521E-01 4.73589E-01 5.23397E-01 5.78443E-01 6.39279E-01 7.06512E-01 7.80817E-01 8.62936E-01 9.53691E-01 1.05399E+00 1.16484E+00 1.28735E+00 1.42274E+00 1.57237E+00 1.73774E+00 1.92050E+00 2.12248E+00 2.34570E+00 2.59240E+00 2.86505E+00 3.16637E+00 3.49938E+00 3.86741E+00 4.27415E+00 4.72366E+00 5.22046E+00 5.76950E+00 6.37628E+00 7.04688E+00 7.78801E+00 8.60708E+00 9.51229E+00 1.05127E+01 1.16183E+01 1.28403E+01 1.41907E+01 3.19843E-03 3.46443E-03 3.75403E-03 4.14710E-03 4.69223E-03 5.39648E-03 6.00939E-03 6.67624E-03 7.34540E-03 8.01897E-03 8.88834E-03 9.49669E-03 9.82265E-03 1.08034E-02 1.19719E-02 1.28843E-02 1.27579E-02 1.40172E-02 1.50061E-02 1.46503E-02 1.57907E-02 1.38832E-02 1.54908E-02 1.69898E-02 1.86833E-02 1.54234E-02 1.69113E-02 1.81951E-02 1.67969E-02 1.84785E-02 1.83719E-02 1.94576E-02 1.84786E-02 1.85009E-02 1.77936E-02 1.63332E-02 1.49720E-02 1.33251E-02 1.31137E-02 1.48995E-02 1.48576E-02 1.30337E-02 1.16504E-02 9.85820E-03 1.15121E-02 1.95863E-02 4.73760E-01 8.94525E+00 8.20000E-01 7.90000E-01 7.60000E-01 7.20000E-01 6.80000E-01 6.30000E-01 6.00000E-01 5.70000E-01 5.40000E-01 5.20000E-01 4.90000E-01 4.80000E-01 4.70000E-01 4.50000E-01 4.30000E-01 4.10000E-01 4.10000E-01 4.00000E-01 3.80000E-01 3.90000E-01 3.70000E-01 4.00000E-01 3.70000E-01 3.60000E-01 3.40000E-01 3.70000E-01 3.60000E-01 3.40000E-01 3.50000E-01 3.40000E-01 3.40000E-01 3.30000E-01 3.40000E-01 3.40000E-01 3.40000E-01 3.60000E-01 3.80000E-01 4.00000E-01 4.00000E-01 3.80000E-01 3.80000E-01 4.00000E-01 4.30000E-01 4.70000E-01 4.30000E-01 3.30000E-01 7.00000E-02 1.00000E-02 "UTG.DAT" ENDS