1 PROGRAM PSYCHE VERSION 6.13 Run on 02/03/05 Input File Specification------------------------Nouri_XP1_account/fromxp1/JEFF30_CD/EVALS/JEFF30N9915_1.ASC Check the Entire File TAPE BEING PROCESSED IS NUMBERED 0 LABEL IS JEFF-3.0 file header. Release April 2002 1 CHECK MATERIAL 9915 (NO WARNINGS DETECTED IN SECTIONS WITHOUT COMMENTS) -------------------------------------------------------------------------------- FILE 1 SECTION 451 99-ES-255 TIT EVAL-AUG87 N.TAKAGI DIST-APR02 ----JEFF-30 MATERIAL 9915 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT SECTION 452 SECTION 455 SECTION 456 -------------------------------------------------------------------------------- FILE 2 SECTION 151 ISOTOPE MASS = 255. HAS NO RESONANCES GIVEN. CHECK ON ISOTOPE PROPERTIES -------------------------------------------------------------------------------- FILE 3 SECTION 1 THERMAL CROSS SECTIONS AND RESONANCE INTEGRALS E = THERMAL SIGMA = 0.00000E+00 SECTION 2 THERMAL CROSS SECTIONS AND RESONANCE INTEGRALS E = THERMAL SIGMA = 0.00000E+00 SECTION 4 SECTION 16 SECTION 17 SECTION 18 THERMAL CROSS SECTIONS AND RESONANCE INTEGRALS E = THERMAL SIGMA = 0.00000E+00 RESONANCE INTEGRAL, 0.5 EV CUTOFF IS 9.32680E+01 SECTION 37 SECTION 51 SECTION 52 SECTION 53 SECTION 91 SECTION 102 THE CALCULATED Q 3.64149E+08 DISSAGREES WITH THE GIVEN Q 4.90169E+06 THERMAL CROSS SECTIONS AND RESONANCE INTEGRALS E = THERMAL SIGMA = -1.99935E+00 RESONANCE INTEGRAL, 0.5 EV CUTOFF IS 2.77483E+02 SECTION 251 -------------------------------------------------------------------------------- FILE 4 SECTION 2 SECTION 16 SECTION 17 SECTION 18 SECTION 37 SECTION 51 SECTION 52 SECTION 53 SECTION 91 -------------------------------------------------------------------------------- FILE 5 SECTION 16 ENERGY GRID TOTAL SECONDARY AVERAGE SECONDARY ENERGY ENERGY NEUTRON ENERGY AVAILABLE ----------- -------------- ----------------- ---------- 6.0074E+06 0.0000E+00 0.0000E+00 4.9520E+01 8.0000E+06 1.6143E+06 8.0717E+05 1.9848E+06 1.0000E+07 1.9965E+06 9.9827E+05 3.9769E+06 1.2000E+07 2.2080E+06 1.1040E+06 5.9690E+06 1.4000E+07 2.4787E+06 1.2394E+06 7.9612E+06 1.6000E+07 2.7167E+06 1.3584E+06 9.9533E+06 1.8000E+07 2.9334E+06 1.4667E+06 1.1945E+07 2.0000E+07 3.1341E+06 1.5670E+06 1.3938E+07 * AVERAGE ENERGY EXCEEDS AVAILABLE ENERGY SECTION 17 ENERGY GRID TOTAL SECONDARY AVERAGE SECONDARY ENERGY ENERGY NEUTRON ENERGY AVAILABLE ----------- -------------- ----------------- ---------- 1.1120E+07 0.0000E+00 0.0000E+00 4.8358E+00 1.2000E+07 1.4778E+06* 4.9259E+05 8.7694E+05 1.4000E+07 3.0075E+06* 1.0025E+06 2.8691E+06 1.6000E+07 3.4864E+06 1.1621E+06 4.8612E+06 1.8000E+07 3.6536E+06 1.2179E+06 6.8533E+06 2.0000E+07 4.0414E+06 1.3471E+06 8.8454E+06 * AVERAGE ENERGY EXCEEDS AVAILABLE ENERGY SECTION 18 ENERGY GRID TOTAL SECONDARY AVERAGE SECONDARY ENERGY ENERGY NEUTRON ENERGY AVAILABLE ----------- -------------- ----------------- ---------- 1.0000E-05 8.3103E+06 2.1496E+06 2.0000E+08 2.0000E+07 1.9059E+07 2.1496E+06 2.1992E+08 * AVERAGE ENERGY EXCEEDS AVAILABLE ENERGY SECTION 37 ENERGY GRID TOTAL SECONDARY AVERAGE SECONDARY ENERGY ENERGY NEUTRON ENERGY AVAILABLE ----------- -------------- ----------------- ---------- 1.7353E+07 0.0000E+00 0.0000E+00 0.0000E+00 1.8000E+07 1.5474E+06* 3.8685E+05 6.4401E+05 2.0000E+07 4.1655E+06* 1.0414E+06 2.6361E+06 * AVERAGE ENERGY EXCEEDS AVAILABLE ENERGY SECTION 91 ENERGY GRID TOTAL SECONDARY AVERAGE SECONDARY ENERGY ENERGY NEUTRON ENERGY AVAILABLE ----------- -------------- ----------------- ---------- 5.0198E+05 0.0000E+00 0.0000E+00 9.3562E-01 2.0000E+06 6.5540E+05 6.5540E+05 1.4921E+06 4.0000E+06 7.3944E+05 7.3944E+05 3.4842E+06 6.0000E+06 9.2807E+05 9.2807E+05 5.4764E+06 8.0000E+06 1.0821E+06 1.0821E+06 7.4685E+06 1.0000E+07 1.2160E+06 1.2160E+06 9.4606E+06 1.2000E+07 1.3361E+06 1.3361E+06 1.1453E+07 1.4000E+07 1.4461E+06 1.4461E+06 1.3445E+07 1.6000E+07 1.5480E+06 1.5480E+06 1.5437E+07 1.8000E+07 1.6435E+06 1.6435E+06 1.7429E+07 2.0000E+07 1.7336E+06 1.7336E+06 1.9421E+07 * AVERAGE ENERGY EXCEEDS AVAILABLE ENERGY