ENTRY L0058 20150313 L026L0058 0 1 SUBENT L0058001 20150127 L026L0058 1 1 BIB 13 106 L0058 1 2 TITLE Photofission and photoneutron cross sections and L0058 1 3 photofission neutron multiplicities for 233U, 234U, L0058 1 4 237Np, and 239Pu. L0058 1 5 AUTHOR (B.L.Berman,J.T.Caldwell,E.J.Dowdy,S.S.Dietrich, L0058 1 6 P.Meyer,R.A.Alvarez) L0058 1 7 REFERENCE (J,PR/C,34,2201,198612) L0058 1 8 #doi:10.1103/PhysRevC.34.2201 L0058 1 9 INSTITUTE (1USALRL,1USAGWU,1USALAS) L0058 1 10 FACILITY (LINAC,1USALRL) L0058 1 11 INC-SOURCE (QMPH,ARAD) Positron annihilation in flight. L0058 1 12 Energy resolution (FWHM) ranged from about 250 keV at L0058 1 13 energies below 10 MeV to about 325 keV at the L0058 1 14 highest energy (E(gamma) about 18 MeV). L0058 1 15 DETECTOR (BF3) Neutron 4pi detector, consisting of a 61-cm L0058 1 16 cube of paraffin containing 48 BF3 tubes arranged in L0058 1 17 four concentric rings of 12 tubes each. L0058 1 18 METHOD (EXTB,RINGR) Direct photoneutron detection. L0058 1 19 Ring-ratio neutron multiplicity measurement. L0058 1 20 A noteworthy feature of this experiment is the use of L0058 1 21 a remotely controlled pneumatic 8-position revolving L0058 1 22 sample changer, which allowed all of the samples, as L0058 1 23 well as a blank sample and a neutron calibration L0058 1 24 source, to be inserted into the center of 4pi L0058 1 25 neutron detector sequentially without changing the L0058 1 26 beam tuning or any other experimental conditions. L0058 1 27 This feature enabled relative cross section L0058 1 28 measurements to be made with a precision of about L0058 1 29 2%. This is much better than the overall absolute L0058 1 30 accuracy of about 5% typical of recent measurements L0058 1 31 near the peak of the giant resonance of medium and L0058 1 32 heavy nuclei. L0058 1 33 ANALYSIS Photoneutrons from each sample and from a L0058 1 34 sample-blank were measured, both with and without L0058 1 35 the annihilation target present. After the recorded L0058 1 36 neutron events were corrected for pileup in the L0058 1 37 detector, the neutron backgrounds (annihilation L0058 1 38 target removed) were substracted for both the L0058 1 39 positron and electron measurements. L0058 1 40 Because the energy spectrum of the annihilation-plus- L0058 1 41 Bremsstrahlung radiation differs from that of purely L0058 1 42 Bremsstrahlung photons, a measured correction was L0058 1 43 applied to the ion-chamber (beam monitor) response L0058 1 44 to normalize the electron data to the positron data. L0058 1 45 The normalized electron data then were substracted L0058 1 46 from the positron data, leaving the neutron counts L0058 1 47 which result only from the annihilation radiation. L0058 1 48 The measured sample-blank data, normalized to equal L0058 1 49 photon flux, were substracted from the target data L0058 1 50 to give the net target results. L0058 1 51 After a small correction for the neutron multiplicity L0058 1 52 in each ring, the data were corrected for the L0058 1 53 energy dependent efficiency of the neutron detector L0058 1 54 using the ring-ratio result for each energy. L0058 1 55 The data were converted to photoneutron cross L0058 1 56 sections by applying the measured ion-chamber L0058 1 57 response per photon, the known number of target L0058 1 58 nuclei in the beam and a small correction for the L0058 1 59 photon attenuation in the sample. L0058 1 60 A multiplicity analysis of the number of neutrons L0058 1 61 recordered in each beam burst allows the (gamma,n) L0058 1 62 an (gamma,2n) yields to be extracted simultaneously L0058 1 63 and independently. L0058 1 64 ERR-ANALYS (ERR-1) subtraction of the positron-bremsstrahlung L0058 1 65 yield (2%), L0058 1 66 (ERR-2) neutron-detector efficiency calibration (3%), L0058 1 67 (ERR-3) photon-flux calibration (5%), L0058 1 68 impurities in the samples (SAMPLE) have been L0058 1 69 accounted for whenever their effect on the results L0058 1 70 exceeded 1%, L0058 1 71 uncertainties resulting from multiplication L0058 1 72 effects in the samples are estimated to be less than L0058 1 73 2%, L0058 1 74 uncertainties resulting from subtraction of the L0058 1 75 copper and nickel backgrounds from (g, 1n) cross L0058 1 76 sections are estimated to be less than 5% for 233U L0058 1 77 and 237Np and less than 10% for 239Pu (at the L0058 1 78 highest energies, for the single-photoneutron cross L0058 1 79 section only), L0058 1 80 the final (g,F) and (g,tot) cross-section values are L0058 1 81 subject to overall systematic uncertainties that do L0058 1 82 not exceed 7 %. L0058 1 83 CORRECTION Corrected for; L0058 1 84 - pileup of counts in the detector, L0058 1 85 - ion-chamber response to electron and positron L0058 1 86 produced radiation, L0058 1 87 - neutron multiplicities in each ring, L0058 1 88 - photon attenuation in the sample. L0058 1 89 COMMENT An interesting result is the complete absence of any L0058 1 90 (gamma,2n) cross section for 238U and 234U. L0058 1 91 The values of nu prompt(E) for 234U agree with those L0058 1 92 measured with neutrons incident on 233U. L0058 1 93 The parameters of the giant dipole resonance deduced L0058 1 94 from the total photonuclear cross sections show that L0058 1 95 these nuclei have large static deformations, as L0058 1 96 expected. The integrated photofission cross sections L0058 1 97 are large (as are the absolute fission L0058 1 98 probabilities), and account for 60 to 80% of the L0058 1 99 total photonuclear absorption strength. L0058 1 100 HISTORY (19891207C) L0058 1 101 (19950407A) BIB Updated. L0058 1 102 (20070914A) Corrected by V.Varlamov: SUBENTs 026 - L0058 1 103 028 added, errors DATA-ERR1 changed to ERR-S, dates. L0058 1 104 (20150127A) Corrected by V.Varlamov: STATUS, SAMPLE, L0058 1 105 COMMON, ERR-ANALYS, REACTION and comment in SUBENT L0058 1 106 015 corrected, DATA in SUBENT 028 substituted, L0058 1 107 SUBENTs 033 - 037 added. L0058 1 108 ENDBIB 106 0 L0058 1 109 COMMON 3 3 L0058 1 110 ERR-1 ERR-2 ERR-3 L0058 1 111 PER-CENT PER-CENT PER-CENT L0058 1 112 2. 3. 5. L0058 1 113 ENDCOMMON 3 0 L0058 1 114 ENDSUBENT 113 0 L0058 199999 SUBENT L0058002 20150127 L026L0058 2 1 BIB 5 9 L0058 2 2 REACTION (92-U-233(G,F),,SIG) L0058 2 3 SAMPLE (92-U-233,ENR=0.974) L0058 2 4 2 samples, 40.31 and 101.06 gram metal disks in L0058 2 5 brass can, 1.91 cm diam., 97.46% 233U. L0058 2 6 ERR-ANALYS (ERR-S) Statistical errors. L0058 2 7 STATUS (BERMN) Converted from Berman compilation. L0058 2 8 Data presented in Fig 4 (c). L0058 2 9 HISTORY (20150127A) Corrected by V.Varlamov: SAMPLE, L0058 2 10 ERR-ANALYS. L0058 2 11 ENDBIB 9 0 L0058 2 12 NOCOMMON 0 0 L0058 2 13 DATA 3 27 L0058 2 14 EN DATA ERR-S L0058 2 15 MEV MB MB L0058 2 16 5.02 1.0 1.2 L0058 2 17 5.51 2.0 1.0 L0058 2 18 6.00 11.0 1.5 L0058 2 19 6.49 19.0 1.4 L0058 2 20 6.98 29.0 1.5 L0058 2 21 7.47 29.0 1.5 L0058 2 22 7.96 36.0 1.5 L0058 2 23 8.45 46.0 1.5 L0058 2 24 8.94 62.0 2.1 L0058 2 25 9.43 97.0 1.4 L0058 2 26 9.92 142.0 2.5 L0058 2 27 10.41 201.0 2.7 L0058 2 28 10.90 252.0 1.1 L0058 2 29 11.40 289.0 4.1 L0058 2 30 11.89 296.0 3.8 L0058 2 31 12.38 335.0 2.9 L0058 2 32 12.87 372.0 4.4 L0058 2 33 13.36 407.0 5.4 L0058 2 34 13.85 419.0 3.7 L0058 2 35 14.34 405.0 6.0 L0058 2 36 14.83 350.0 6.3 L0058 2 37 15.32 297.0 3.9 L0058 2 38 15.81 266.0 5.4 L0058 2 39 16.30 217.0 5.0 L0058 2 40 16.79 179.0 2.0 L0058 2 41 17.28 157.0 3.9 L0058 2 42 17.77 142.0 4.0 L0058 2 43 ENDDATA 29 0 L0058 2 44 ENDSUBENT 43 0 L0058 299999 SUBENT L0058003 20150127 L026L0058 3 1 BIB 5 13 L0058 3 2 REACTION ((92-U-233(G,N)92-U-232,,SIG)+ L0058 3 3 (92-U-233(G,N+P)91-PA-231,,SIG)) L0058 3 4 Threshold of the reaction (gamma,n+p) is about 13.0 L0058 3 5 MeV. L0058 3 6 Fission neutron contribution is excluded. L0058 3 7 SAMPLE (92-U-233,ENR=0.974) L0058 3 8 2 samples, 40.31 and 101.06 gram metal disks in L0058 3 9 brass can, 1.91 cm diam., 97.46% 233U. L0058 3 10 ERR-ANALYS (ERR-S) Statistical errors. L0058 3 11 STATUS (BERMN) Converted from Berman compilation. L0058 3 12 Data presented in Fig 4 (b). L0058 3 13 HISTORY (20150127A) Corrected by V.Varlamov: SAMPLE, L0058 3 14 ERR-ANALYS. L0058 3 15 ENDBIB 13 0 L0058 3 16 NOCOMMON 0 0 L0058 3 17 DATA 3 27 L0058 3 18 EN DATA ERR-S L0058 3 19 MEV MB MB L0058 3 20 5.02 1.7 7.7 L0058 3 21 5.51 6.6 6.9 L0058 3 22 6.00 2.0 5.6 L0058 3 23 6.49 -1.5 4.4 L0058 3 24 6.98 0.0 3.5 L0058 3 25 7.47 5.6 3.5 L0058 3 26 7.96 13.0 2.5 L0058 3 27 8.45 15.0 3.3 L0058 3 28 8.94 25.0 4.2 L0058 3 29 9.43 34.0 2.4 L0058 3 30 9.92 59.0 6.1 L0058 3 31 10.41 99.0 5.7 L0058 3 32 10.90 131.0 2.7 L0058 3 33 11.40 134.0 6.9 L0058 3 34 11.89 110.0 6.5 L0058 3 35 12.38 77.0 5.3 L0058 3 36 12.87 59.0 7.9 L0058 3 37 13.36 64.0 10.0 L0058 3 38 13.85 45.0 7.0 L0058 3 39 14.34 45.0 12.0 L0058 3 40 14.83 24.0 13.0 L0058 3 41 15.32 56.0 7.9 L0058 3 42 15.81 31.0 11.0 L0058 3 43 16.30 47.0 10.0 L0058 3 44 16.79 63.0 4.9 L0058 3 45 17.28 23.0 9.2 L0058 3 46 17.77 42.0 9.4 L0058 3 47 ENDDATA 29 0 L0058 3 48 ENDSUBENT 47 0 L0058 399999 SUBENT L0058004 20150127 L026L0058 4 1 BIB 5 11 L0058 4 2 REACTION (92-U-233(G,X)0-NN-1,,SIG) L0058 4 3 The sum: (G,N)+(G,N+P)+2(G,2N)+nu(G,F). L0058 4 4 SAMPLE (92-U-233,ENR=0.974) L0058 4 5 2 samples, 40.31 and 101.06 gram metal disks in L0058 4 6 brass can, 1.91 cm diam., 97.46% 233U. L0058 4 7 ERR-ANALYS (DATA-ERR) Uncertainties for total photonuclear cross L0058 4 8 sections computed by adding in quadrature those for L0058 4 9 the partial cross sections. L0058 4 10 STATUS (BERMN) Converted from Berman compilation. L0058 4 11 HISTORY (20150127A) Corrected by V.Varlamov: REACTION comment L0058 4 12 substituted, SAMPLE, DATA-ERR, ERR-ANALYS. L0058 4 13 ENDBIB 11 0 L0058 4 14 NOCOMMON 0 0 L0058 4 15 DATA 3 27 L0058 4 16 EN DATA DATA-ERR L0058 4 17 MEV MB MB L0058 4 18 5.02 4.8 8.1 L0058 4 19 5.51 11.0 1.0 L0058 4 20 6.00 26.0 6.5 L0058 4 21 6.49 42.0 5.4 L0058 4 22 6.98 69.0 4.9 L0058 4 23 7.47 77.0 5.1 L0058 4 24 7.96 105.0 4.5 L0058 4 25 8.45 136.0 5.0 L0058 4 26 8.94 193.0 7.0 L0058 4 27 9.43 302.0 4.6 L0058 4 28 9.92 467.0 9.4 L0058 4 29 10.41 693.0 9.9 L0058 4 30 10.90 898.0 4.7 L0058 4 31 11.40 1037.0 14.0 L0058 4 32 11.89 1059.0 14.0 L0058 4 33 12.38 1179.0 11.0 L0058 4 34 12.87 1314.0 17.0 L0058 4 35 13.36 1471.0 21.0 L0058 4 36 13.85 1528.0 15.0 L0058 4 37 14.34 1512.0 25.0 L0058 4 38 14.83 1321.0 27.0 L0058 4 39 15.32 1181.0 17.0 L0058 4 40 15.81 1061.0 23.0 L0058 4 41 16.30 905.0 22.0 L0058 4 42 16.79 788.0 9.4 L0058 4 43 17.28 670.0 19.0 L0058 4 44 17.77 639.0 19.0 L0058 4 45 ENDDATA 29 0 L0058 4 46 ENDSUBENT 45 0 L0058 499999 SUBENT L0058005 20150127 L026L0058 5 1 BIB 5 11 L0058 5 2 REACTION (92-U-234(G,F),,SIG) L0058 5 3 SAMPLE (92-U-234,ENR=0.9984) L0058 5 4 (92-U-234,ENR=0.9978) L0058 5 5 2 samples, oxide powder in lucite cylinder, 2.54 cm L0058 5 6 diam.: 3.325 grams (99.84% 234U) and 12.525 grams L0058 5 7 (99.78% 234U). L0058 5 8 ERR-ANALYS (ERR-S) Statistical errors. L0058 5 9 STATUS (BERMN) Converted from Berman compilation. L0058 5 10 Data presented in Fig 5 (c). L0058 5 11 HISTORY (20150127A) Corrected by V.Varlamov: SAMPLE, L0058 5 12 ERR-ANALYS. L0058 5 13 ENDBIB 11 0 L0058 5 14 NOCOMMON 0 0 L0058 5 15 DATA 3 27 L0058 5 16 EN DATA ERR-S L0058 5 17 MEV MB MB L0058 5 18 6.98 25.2 4.5 L0058 5 19 7.47 34.4 4.6 L0058 5 20 7.96 37.9 3.4 L0058 5 21 8.45 50.5 5.7 L0058 5 22 8.94 58.5 5.7 L0058 5 23 9.43 99.8 4.6 L0058 5 24 9.92 155.0 8.4 L0058 5 25 10.41 189.0 5.7 L0058 5 26 10.90 236.0 3.4 L0058 5 27 11.39 250.0 9.2 L0058 5 28 11.88 234.0 9.2 L0058 5 29 12.37 239.0 5.7 L0058 5 30 12.74 255.0 3.0 L0058 5 31 12.86 270.0 10.0 L0058 5 32 12.98 297.0 3.3 L0058 5 33 13.22 319.0 3.7 L0058 5 34 13.35 325.0 10.0 L0058 5 35 13.47 327.0 4.3 L0058 5 36 13.84 379.0 6.9 L0058 5 37 14.33 384.0 10.0 L0058 5 38 14.82 361.0 10.0 L0058 5 39 15.31 310.0 6.9 L0058 5 40 15.80 260.0 9.2 L0058 5 41 16.29 216.0 9.2 L0058 5 42 16.78 165.0 5.7 L0058 5 43 17.76 122.0 8.0 L0058 5 44 18.25 122.0 8.0 L0058 5 45 ENDDATA 29 0 L0058 5 46 ENDSUBENT 45 0 L0058 599999 SUBENT L0058006 20150127 L026L0058 6 1 BIB 5 13 L0058 6 2 REACTION ((92-U-234(G,N)92-U-233,,SIG)+ L0058 6 3 (92-U-234(G,N+P)91-PA-232,,SIG)) L0058 6 4 Fission neutron contribution is excluded. L0058 6 5 SAMPLE (92-U-234,ENR=0.9984) L0058 6 6 (92-U-234,ENR=0.9978) L0058 6 7 2 samples, oxide powder in lucite cylinder, 2.54 cm L0058 6 8 diam.: 3.325 grams (99.84% 234U) and 12.525 grams L0058 6 9 (99.78% 234U). L0058 6 10 ERR-ANALYS (ERR-S) Statistical errors. L0058 6 11 STATUS (BERMN) Converted from Berman compilation. L0058 6 12 Data presented in Fig 5 (b). L0058 6 13 HISTORY (20150127A) Corrected by V.Varlamov: SAMPLE, L0058 6 14 ERR-ANALYS. L0058 6 15 ENDBIB 13 0 L0058 6 16 NOCOMMON 0 0 L0058 6 17 DATA 3 27 L0058 6 18 EN DATA ERR-S L0058 6 19 MEV MB MB L0058 6 20 6.98 57.4 70.0 L0058 6 21 7.47 35.6 60.0 L0058 6 22 7.96 122.0 57.0 L0058 6 23 8.45 64.2 56.0 L0058 6 24 8.94 89.5 53.0 L0058 6 25 9.43 31.0 52.0 L0058 6 26 9.92 44.7 47.0 L0058 6 27 10.41 167.0 23.0 L0058 6 28 10.90 240.0 15.0 L0058 6 29 11.39 224.0 38.0 L0058 6 30 11.88 249.0 36.0 L0058 6 31 12.37 210.0 31.0 L0058 6 32 12.74 179.0 12.0 L0058 6 33 12.86 103.0 38.0 L0058 6 34 12.98 163.0 12.0 L0058 6 35 13.22 146.0 13.0 L0058 6 36 13.35 87.0 36.0 L0058 6 37 13.47 129.0 17.0 L0058 6 38 13.84 68.0 32.0 L0058 6 39 14.33 83.0 34.0 L0058 6 40 14.82 61.0 34.0 L0058 6 41 15.31 24.0 25.0 L0058 6 42 15.80 -18.9 31.0 L0058 6 43 16.29 -11.6 29.0 L0058 6 44 16.78 32.0 24.0 L0058 6 45 17.76 56.0 42.0 L0058 6 46 18.25 40.0 26.0 L0058 6 47 ENDDATA 29 0 L0058 6 48 ENDSUBENT 47 0 L0058 699999 SUBENT L0058007 20150127 L026L0058 7 1 BIB 5 13 L0058 7 2 REACTION (92-U-234(G,X)0-NN-1,,SIG) L0058 7 3 The sum: (G,N)+(G,N+P)+2(G,2N)+nu(G,F). L0058 7 4 SAMPLE (92-U-234,ENR=0.9984) L0058 7 5 (92-U-234,ENR=0.9978) L0058 7 6 2 samples, oxide powder in lucite cylinder, 2.54 cm L0058 7 7 diam.: 3.325 grams (99.84% 234U) and 12.525 grams L0058 7 8 (99.78% 234U). L0058 7 9 ERR-ANALYS (DATA-ERR) Uncertainties for total photonuclear cross L0058 7 10 sections computed by adding in quadrature those for L0058 7 11 the partial cross sections. L0058 7 12 STATUS (BERMN) Converted from Berman compilation. L0058 7 13 HISTORY (20150127A) Corrected by V.Varlamov: REACTION comment L0058 7 14 substituted, SAMPLE, DATA-ERR, ERR-ANALYS. L0058 7 15 ENDBIB 13 0 L0058 7 16 NOCOMMON 0 0 L0058 7 17 DATA 3 27 L0058 7 18 EN DATA DATA-ERR L0058 7 19 MEV MB MB L0058 7 20 6.98 121.0 71.0 L0058 7 21 7.47 124.0 61.0 L0058 7 22 7.96 222.0 58.0 L0058 7 23 8.45 201.0 58.0 L0058 7 24 8.94 251.0 55.0 L0058 7 25 9.43 314.0 54.0 L0058 7 26 9.92 494.0 52.0 L0058 7 27 10.41 727.0 29.0 L0058 7 28 10.90 955.0 18.0 L0058 7 29 11.39 998.0 47.0 L0058 7 30 11.88 988.0 46.0 L0058 7 31 12.37 981.0 36.0 L0058 7 32 12.74 1014.0 16.0 L0058 7 33 12.86 991.0 50.0 L0058 7 34 12.98 1145.0 16.0 L0058 7 35 13.22 1211.0 18.0 L0058 7 36 13.35 1177.0 49.0 L0058 7 37 13.47 1231.0 22.0 L0058 7 38 13.84 1364.0 40.0 L0058 7 39 14.33 1421.0 49.0 L0058 7 40 14.82 1342.0 49.0 L0058 7 41 15.31 1144.0 35.0 L0058 7 42 15.80 938.0 46.0 L0058 7 43 16.29 797.0 45.0 L0058 7 44 16.78 660.0 32.0 L0058 7 45 17.76 537.0 53.0 L0058 7 46 18.25 528.0 41.0 L0058 7 47 ENDDATA 29 0 L0058 7 48 ENDSUBENT 47 0 L0058 799999 SUBENT L0058008 20150127 L026L0058 8 1 BIB 5 11 L0058 8 2 REACTION ((93-NP-237(G,N)93-NP-236,,SIG)+ L0058 8 3 (93-NP-237(G,N+P)92-U-235,,SIG)) L0058 8 4 Threshold of the reaction (gamma,n+p) is 11.4 MeV. L0058 8 5 Fission neutron contribution is excluded. L0058 8 6 SAMPLE Metal sample in brass cylinder, 2.86 cm diam., 45.62 L0058 8 7 grams, 100% 237Np. L0058 8 8 ERR-ANALYS (ERR-S) Statistical errors. L0058 8 9 STATUS (BERMN) Converted from Berman compilation. L0058 8 10 Data presented in Fig 6 (b). L0058 8 11 HISTORY (20150127A) Corrected by V.Varlamov: STATUS, L0058 8 12 ERR-ANALYS. L0058 8 13 ENDBIB 11 0 L0058 8 14 NOCOMMON 0 0 L0058 8 15 DATA 3 27 L0058 8 16 EN DATA ERR-S L0058 8 17 MEV MB MB L0058 8 18 5.51 1.6 16.0 L0058 8 19 6.00 1.6 13.0 L0058 8 20 6.49 -1.0 8.9 L0058 8 21 6.98 0.5 6.3 L0058 8 22 7.47 12.0 4.2 L0058 8 23 7.96 23.0 5.8 L0058 8 24 8.45 32.0 7.4 L0058 8 25 8.94 33.0 7.9 L0058 8 26 9.43 56.0 5.3 L0058 8 27 9.92 87.0 9.6 L0058 8 28 10.41 138.0 10.0 L0058 8 29 10.90 185.0 5.3 L0058 8 30 11.40 198.0 9.1 L0058 8 31 11.89 196.0 12.0 L0058 8 32 12.38 212.0 9.1 L0058 8 33 12.87 180.0 13.0 L0058 8 34 13.36 208.0 18.0 L0058 8 35 13.85 160.0 14.0 L0058 8 36 14.34 102.0 22.0 L0058 8 37 14.83 108.0 25.0 L0058 8 38 15.32 117.0 15.0 L0058 8 39 15.81 62.0 20.0 L0058 8 40 16.30 66.0 19.0 L0058 8 41 16.79 62.0 13.0 L0058 8 42 17.28 40.0 17.0 L0058 8 43 17.77 87.0 17.0 L0058 8 44 18.26 46.0 39.0 L0058 8 45 ENDDATA 29 0 L0058 8 46 ENDSUBENT 45 0 L0058 899999 SUBENT L0058009 20150127 L026L0058 9 1 BIB 5 11 L0058 9 2 REACTION ((93-NP-237(G,2N)93-NP-235,,SIG)+ L0058 9 3 (93-NP-237(G,2N+P)92-U-234,,SIG)) L0058 9 4 Threshold of the reaction (gamma,2n+p) is 16.7 MeV. L0058 9 5 Fission neutron contribution is excluded. L0058 9 6 SAMPLE Metal sample in brass cylinder, 2.86 cm diam., 45.62 L0058 9 7 grams, 100% 237Np. L0058 9 8 ERR-ANALYS (ERR-S) Statistical errors. L0058 9 9 STATUS (BERMN) Converted from Berman compilation. L0058 9 10 Data presented in Fig 6 (c). L0058 9 11 HISTORY (19950407A) Corrected by V.Varlamov: REACTION, L0058 9 12 STATUS? ERR-ANALYS. L0058 9 13 ENDBIB 11 0 L0058 9 14 NOCOMMON 0 0 L0058 9 15 DATA 3 14 L0058 9 16 EN DATA ERR-S L0058 9 17 MEV MB MB L0058 9 18 11.89 1.1 12.0 L0058 9 19 12.38 -6.5 9.1 L0058 9 20 12.87 19.0 13.0 L0058 9 21 13.36 46.0 18.0 L0058 9 22 13.85 71.0 13.0 L0058 9 23 14.34 130.0 21.0 L0058 9 24 14.83 100.0 23.0 L0058 9 25 15.32 77.0 14.0 L0058 9 26 15.81 100.0 19.0 L0058 9 27 16.30 59.0 18.0 L0058 9 28 16.79 21.0 12.0 L0058 9 29 17.28 59.0 17.0 L0058 9 30 17.77 4.4 17.0 L0058 9 31 18.26 61.0 37.0 L0058 9 32 ENDDATA 16 0 L0058 9 33 ENDSUBENT 32 0 L0058 999999 SUBENT L0058010 20150127 L026L0058 10 1 BIB 5 8 L0058 10 2 REACTION (93-NP-237(G,F),,SIG) L0058 10 3 SAMPLE Metal sample in brass cylinder, 2.86 cm diam., 45.62 L0058 10 4 grams, 100% 237Np. L0058 10 5 ERR-ANALYS (ERR-S) Statistical errors. L0058 10 6 STATUS (BERMN) Converted from Berman compilation. L0058 10 7 Data presented in Fig 6 (d). L0058 10 8 HISTORY (20150127A) Corrected by V.Varlamov: STATUS, L0058 10 9 ERR-ANALYS. L0058 10 10 ENDBIB 8 0 L0058 10 11 NOCOMMON 0 0 L0058 10 12 DATA 3 27 L0058 10 13 EN DATA ERR-S L0058 10 14 MEV MB MB L0058 10 15 5.51 5.7 12.0 L0058 10 16 6.00 17.0 9.9 L0058 10 17 6.49 30.0 6.8 L0058 10 18 6.98 38.0 4.7 L0058 10 19 7.47 40.0 4.7 L0058 10 20 7.96 39.0 3.7 L0058 10 21 8.45 46.0 4.7 L0058 10 22 8.94 76.0 5.3 L0058 10 23 9.43 104.0 3.2 L0058 10 24 9.92 166.0 5.8 L0058 10 25 10.41 238.0 5.9 L0058 10 26 10.90 278.0 3.2 L0058 10 27 11.40 280.0 5.4 L0058 10 28 11.89 263.0 7.0 L0058 10 29 12.38 258.0 4.8 L0058 10 30 12.87 283.0 7.0 L0058 10 31 13.36 325.0 8.1 L0058 10 32 13.85 350.0 6.0 L0058 10 33 14.34 338.0 9.2 L0058 10 34 14.83 310.0 9.2 L0058 10 35 15.32 261.0 5.5 L0058 10 36 15.81 215.0 7.1 L0058 10 37 16.30 187.0 7.1 L0058 10 38 16.79 168.0 4.4 L0058 10 39 17.28 140.0 6.1 L0058 10 40 17.77 136.0 6.1 L0058 10 41 18.26 117.0 13.0 L0058 10 42 ENDDATA 29 0 L0058 10 43 ENDSUBENT 42 0 L0058 1099999 SUBENT L0058011 20150127 L026L0058 11 1 BIB 5 10 L0058 11 2 REACTION (93-NP-237(G,X)0-NN-1,,SIG) L0058 11 3 The sum: (G,N)+(G,N+P)+2(G,2N)+2(G,2N+P)+nu(G,F). L0058 11 4 ERR-ANALYS (DATA-ERR) Uncertainties for total photonuclear cross L0058 11 5 sections computed by adding in quadrature those for L0058 11 6 the partial cross sections. L0058 11 7 SAMPLE Metal sample in brass cylinder, 2.86 cm diam., 45.62 L0058 11 8 grams, 100% 237Np. L0058 11 9 STATUS (BERMN) Converted from Berman compilation. L0058 11 10 HISTORY (20150127A) Corrected by V.Varlamov: REACTION comment L0058 11 11 substituted, DATA-ERR, ERR-ANALYS. L0058 11 12 ENDBIB 10 0 L0058 11 13 NOCOMMON 0 0 L0058 11 14 DATA 3 27 L0058 11 15 EN DATA DATA-ERR L0058 11 16 MEV MB MB L0058 11 17 5.51 14.0 31.0 L0058 11 18 6.00 41.0 27.0 L0058 11 19 6.49 72.0 19.0 L0058 11 20 6.98 98.0 14.0 L0058 11 21 7.47 119.0 13.0 L0058 11 22 7.96 131.0 12.0 L0058 11 23 8.45 165.0 15.0 L0058 11 24 8.94 261.0 18.0 L0058 11 25 9.43 380.0 11.0 L0058 11 26 9.92 623.0 21.0 L0058 11 27 10.41 932.0 22.0 L0058 11 28 10.90 1144.0 12.0 L0058 11 29 11.40 1195.0 21.0 L0058 11 30 11.89 1163.0 37.0 L0058 11 31 12.38 1175.0 27.0 L0058 11 32 12.87 1320.0 40.0 L0058 11 33 13.36 1601.0 52.0 L0058 11 34 13.85 1742.0 38.0 L0058 11 35 14.34 1790.0 61.0 L0058 11 36 14.83 1652.0 66.0 L0058 11 37 15.32 1432.0 40.0 L0058 11 38 15.81 1242.0 54.0 L0058 11 39 16.30 1057.0 53.0 L0058 11 40 16.79 907.0 34.0 L0058 11 41 17.28 843.0 48.0 L0058 11 42 17.77 776.0 49.0 L0058 11 43 18.26 766.0 107.0 L0058 11 44 ENDDATA 29 0 L0058 11 45 ENDSUBENT 44 0 L0058 1199999 SUBENT L0058012 20150127 L026L0058 12 1 BIB 5 16 L0058 12 2 REACTION ((94-PU-239(G,N)94-PU-238,,SIG)+ L0058 12 3 (94-PU-239(G,N+P)93-NP-237,,SIG)) L0058 12 4 Threshold of the reaction (gamma,n+p) is 11.6 MeV. L0058 12 5 Fission neutron contribution is excluded. L0058 12 6 SAMPLE (94-PU-239,ENR=0.9767) L0058 12 7 (94-PU-239,ENR=0.9992) L0058 12 8 2 samples: L0058 12 9 - metal disk in nickel can, 2.29 cm diam., 4.98 L0058 12 10 grams, 97.67% 239Pu, L0058 12 11 - metal cube in steel can, 1.25 cm edge, 29.91 L0058 12 12 grams, 99.92% 239Pu. L0058 12 13 ERR-ANALYS (ERR-S) Statistical errors. L0058 12 14 STATUS (BERMN) Converted from Berman compilation. L0058 12 15 Data presented in Fig 7 (b). L0058 12 16 HISTORY (20150127A) Corrected by V.Varlamov: SAMPLE, STATUS, L0058 12 17 ERR-ANALYS. L0058 12 18 ENDBIB 16 0 L0058 12 19 NOCOMMON 0 0 L0058 12 20 DATA 3 33 L0058 12 21 EN DATA ERR-S L0058 12 22 MEV MB MB L0058 12 23 6.00 5.2 2.8 L0058 12 24 6.20 0.9 1.4 L0058 12 25 6.34 4.6 1.4 L0058 12 26 6.50 1.4 1.4 L0058 12 27 6.74 7.6 2.9 L0058 12 28 6.98 3.3 1.9 L0058 12 29 7.23 9.0 2.4 L0058 12 30 7.47 9.0 2.4 L0058 12 31 7.72 5.3 1.9 L0058 12 32 7.96 12.0 2.4 L0058 12 33 8.21 18.0 2.4 L0058 12 34 8.45 18.0 1.9 L0058 12 35 8.70 17.0 4.9 L0058 12 36 8.94 31.0 4.8 L0058 12 37 9.19 30.0 4.4 L0058 12 38 9.43 44.0 4.3 L0058 12 39 9.68 45.0 7.9 L0058 12 40 9.92 72.0 5.4 L0058 12 41 10.41 131.0 17.0 L0058 12 42 10.90 150.0 10.0 L0058 12 43 11.39 208.0 22.0 L0058 12 44 11.88 192.0 20.0 L0058 12 45 12.37 182.0 15.0 L0058 12 46 12.86 133.0 30.0 L0058 12 47 13.35 46.0 29.0 L0058 12 48 13.84 76.0 20.0 L0058 12 49 14.33 39.0 24.0 L0058 12 50 14.82 2.0 33.0 L0058 12 51 15.31 -55.0 20.0 L0058 12 52 15.80 -68.0 29.0 L0058 12 53 16.29 -26.0 31.0 L0058 12 54 16.78 36.0 17.0 L0058 12 55 17.76 41.0 18.0 L0058 12 56 ENDDATA 35 0 L0058 12 57 ENDSUBENT 56 0 L0058 1299999 SUBENT L0058013 20150127 L026L0058 13 1 BIB 5 14 L0058 13 2 REACTION (94-PU-239(G,2N)94-PU-237,,SIG) L0058 13 3 Fission neutron contribution is excluded. L0058 13 4 SAMPLE (94-PU-239,ENR=0.9767) L0058 13 5 (94-PU-239,ENR=0.9992) L0058 13 6 2 samples: L0058 13 7 - metal disk in nickel can, 2.29 cm diam., 4.98 L0058 13 8 grams, 97.67% 239Pu, L0058 13 9 - metal cube in steel can, 1.25 cm edge, 29.91 L0058 13 10 grams, 99.92% 239Pu. L0058 13 11 ERR-ANALYS (ERR-S) Statistical errors. L0058 13 12 STATUS (BERMN) Converted from Berman compilation. L0058 13 13 Data presented in Fig 7 (c). L0058 13 14 HISTORY (20150127A) Corrected by V.Varlamov: SAMPLE, STATUS, L0058 13 15 ERR-ANALYS. L0058 13 16 ENDBIB 14 0 L0058 13 17 NOCOMMON 0 0 L0058 13 18 DATA 3 10 L0058 13 19 EN DATA ERR-S L0058 13 20 MEV MB MB L0058 13 21 12.86 5.0 28.0 L0058 13 22 13.35 64.0 27.0 L0058 13 23 13.84 35.0 18.0 L0058 13 24 14.33 61.0 20.0 L0058 13 25 14.82 17.0 30.0 L0058 13 26 15.31 41.0 18.0 L0058 13 27 15.80 0.0 26.0 L0058 13 28 16.29 22.0 29.0 L0058 13 29 16.78 17.0 16.0 L0058 13 30 17.76 44.0 17.0 L0058 13 31 ENDDATA 12 0 L0058 13 32 ENDSUBENT 31 0 L0058 1399999 SUBENT L0058014 20150127 L026L0058 14 1 BIB 5 13 L0058 14 2 REACTION (94-PU-239(G,F),,SIG) L0058 14 3 SAMPLE (94-PU-239,ENR=0.9767) L0058 14 4 (94-PU-239,ENR=0.9992) L0058 14 5 2 samples: L0058 14 6 - metal disk in nickel can, 2.29 cm diam., 4.98 L0058 14 7 grams, 97.67% 239Pu, L0058 14 8 - metal cube in steel can, 1.25 cm edge, 29.91 L0058 14 9 grams, 99.92% 239Pu. L0058 14 10 ERR-ANALYS (ERR-S) Statistical errors. L0058 14 11 STATUS (BERMN) Converted from Berman compilation. L0058 14 12 Data presented in Fig 7 (d). L0058 14 13 HISTORY (20150127A) Corrected by V.Varlamov: SAMPLE, STATUS, L0058 14 14 ERR-ANALYS. L0058 14 15 ENDBIB 13 0 L0058 14 16 NOCOMMON 0 0 L0058 14 17 DATA 3 33 L0058 14 18 EN DATA ERR-S L0058 14 19 MEV MB MB L0058 14 20 6.00 4.2 1.4 L0058 14 21 6.20 8.9 1.4 L0058 14 22 6.34 10.0 1.0 L0058 14 23 6.50 14.0 1.0 L0058 14 24 6.74 15.0 1.4 L0058 14 25 6.98 19.0 1.4 L0058 14 26 7.23 20.0 1.4 L0058 14 27 7.47 24.0 1.4 L0058 14 28 7.72 31.0 1.4 L0058 14 29 7.96 34.0 1.4 L0058 14 30 8.21 38.0 1.4 L0058 14 31 8.45 45.0 1.0 L0058 14 32 8.70 57.0 2.9 L0058 14 33 8.94 62.0 2.9 L0058 14 34 9.19 78.8 2.9 L0058 14 35 9.43 94.0 2.8 L0058 14 36 9.68 117.0 4.9 L0058 14 37 9.92 146.0 3.2 L0058 14 38 10.41 216.0 9.6 L0058 14 39 10.90 250.0 4.3 L0058 14 40 11.39 278.0 12.0 L0058 14 41 11.88 293.0 10.0 L0058 14 42 12.37 271.0 7.0 L0058 14 43 12.86 299.0 14.0 L0058 14 44 13.35 335.0 13.0 L0058 14 45 13.84 359.0 8.4 L0058 14 46 14.33 345.0 12.0 L0058 14 47 14.82 308.0 13.0 L0058 14 48 15.31 271.0 7.7 L0058 14 49 15.80 220.0 10.0 L0058 14 50 16.29 175.0 11.0 L0058 14 51 16.78 159.0 5.7 L0058 14 52 17.76 82.0 6.1 L0058 14 53 ENDDATA 35 0 L0058 14 54 ENDSUBENT 53 0 L0058 1499999 SUBENT L0058015 20150127 L026L0058 15 1 BIB 5 15 L0058 15 2 REACTION (94-PU-239(G,X)0-NN-1,,SIG) L0058 15 3 The sum: (G,N)+(G,N+P)+2(G,2N)+nu(G,F). L0058 15 4 SAMPLE (94-PU-239,ENR=0.9767) L0058 15 5 (94-PU-239,ENR=0.9992) L0058 15 6 2 samples: L0058 15 7 - metal disk in nickel can, 2.29 cm diam., 4.98 L0058 15 8 grams, 97.67% 239Pu, L0058 15 9 - metal cube in steel can, 1.25 cm edge, 29.91 L0058 15 10 grams, 99.92% 239Pu. L0058 15 11 ERR-ANALYS (DATA-ERR) Uncertainties for total photonuclear cross L0058 15 12 sections computed by adding in quadrature those for L0058 15 13 the partial cross sections. L0058 15 14 STATUS (BERMN) Converted from Berman compilation. L0058 15 15 HISTORY (20150127A) Corrected by V.Varlamov: UNW deleted, L0058 15 16 comment substituted, SAMPLE, DATA-ERR, ERR-ANALYS. L0058 15 17 ENDBIB 15 0 L0058 15 18 NOCOMMON 0 0 L0058 15 19 DATA 3 33 L0058 15 20 EN DATA DATA-ERR L0058 15 21 MEV MB MB L0058 15 22 6.00 17.0 4.9 L0058 15 23 6.20 27.0 4.3 L0058 15 24 6.34 29.0 3.4 L0058 15 25 6.50 42.0 3.1 L0058 15 26 6.74 52.0 5.1 L0058 15 27 6.98 38.0 4.6 L0058 15 28 7.23 70.0 4.9 L0058 15 29 7.47 84.0 5.0 L0058 15 30 7.72 103.0 4.8 L0058 15 31 7.96 121.0 5.0 L0058 15 32 8.21 141.0 5.1 L0058 15 33 8.45 166.0 3.7 L0058 15 34 8.70 207.0 11.0 L0058 15 35 8.94 240.0 11.0 L0058 15 36 9.19 297.0 11.0 L0058 15 37 9.43 369.0 11.0 L0058 15 38 9.68 455.0 19.0 L0058 15 39 9.92 592.0 13.0 L0058 15 40 10.41 917.0 39.0 L0058 15 41 10.90 1082.0 19.0 L0058 15 42 11.39 1269.0 51.0 L0058 15 43 11.88 1336.0 44.0 L0058 15 44 12.37 1264.0 32.0 L0058 15 45 12.86 1363.0 85.0 L0058 15 46 13.35 1571.0 82.0 L0058 15 47 13.84 1674.0 55.0 L0058 15 48 14.33 1660.0 70.0 L0058 15 49 14.82 1402.0 90.0 L0058 15 50 15.31 1252.0 54.0 L0058 15 51 15.80 946.0 75.0 L0058 15 52 16.29 840.0 84.0 L0058 15 53 16.78 831.0 45.0 L0058 15 54 17.76 536.0 49.0 L0058 15 55 ENDDATA 35 0 L0058 15 56 ENDSUBENT 55 0 L0058 1599999 SUBENT L0058016 20150127 L026L0058 16 1 BIB 4 7 L0058 16 2 REACTION ((92-U-233(G,N)92-U-232,,INT)+ L0058 16 3 (92-U-233(G,N+P)91-PA-231,,INT)) L0058 16 4 Fission neutron contribution is excluded. L0058 16 5 ERR-ANALYS No information. L0058 16 6 STATUS (DEP,L0058003) Data taken from TABLE 9 of article L0058 16 7 HISTORY (20150127A) Corrected by V.Varlamov: DATA and L0058 16 8 DATA-UNIT substituted. L0058 16 9 ENDBIB 7 0 L0058 16 10 NOCOMMON 0 0 L0058 16 11 DATA 3 1 L0058 16 12 EN-MIN EN-MAX DATA L0058 16 13 MEV MEV B*MEV L0058 16 14 5.753 17.8 .58 L0058 16 15 ENDDATA 3 0 L0058 16 16 ENDSUBENT 15 0 L0058 1699999 SUBENT L0058017 20150127 L026L0058 17 1 BIB 4 5 L0058 17 2 REACTION (92-U-233(G,F),,INT) L0058 17 3 ERR-ANALYS No information. L0058 17 4 STATUS (DEP,L0058002) Data taken from TABLE 9 of article L0058 17 5 HISTORY (20150127A) Corrected by V.Varlamov: DATA and L0058 17 6 DATA-UNIT substituted. L0058 17 7 ENDBIB 5 0 L0058 17 8 NOCOMMON 0 0 L0058 17 9 DATA 3 1 L0058 17 10 EN-MIN EN-MAX DATA L0058 17 11 MEV MEV B*MEV L0058 17 12 5.7 17.8 2.44 L0058 17 13 ENDDATA 3 0 L0058 17 14 ENDSUBENT 13 0 L0058 1799999 SUBENT L0058018 20150127 L026L0058 18 1 BIB 4 5 L0058 18 2 REACTION (92-U-234(G,F),,INT) L0058 18 3 ERR-ANALYS No information. L0058 18 4 STATUS (DEP,L0058005) Data taken from TABLE 9 of article L0058 18 5 HISTORY (20150127A) Corrected by V.Varlamov: DATA and L0058 18 6 DATA-UNIT substituted. L0058 18 7 ENDBIB 5 0 L0058 18 8 NOCOMMON 0 0 L0058 18 9 DATA 3 1 L0058 18 10 EN-MIN EN-MAX DATA L0058 18 11 MEV MEV B*MEV L0058 18 12 6.0 18.3 2.26 L0058 18 13 ENDDATA 3 0 L0058 18 14 ENDSUBENT 13 0 L0058 1899999 SUBENT L0058019 20150127 L026L0058 19 1 BIB 4 8 L0058 19 2 REACTION ((92-U-234(G,N)92-U-233,,INT)+ L0058 19 3 (92-U-234(G,N+P)91-PA-232,,INT)) L0058 19 4 Threshold of the reaction (gamma,n+p) is 13.1 MeV. L0058 19 5 Fission neutron contribution is excluded. L0058 19 6 ERR-ANALYS No information. L0058 19 7 STATUS (DEP,L0058006) Data taken from TABLE 9 of article L0058 19 8 HISTORY (20150127A) Corrected by V.Varlamov: DATA and L0058 19 9 DATA-UNIT substituted. L0058 19 10 ENDBIB 8 0 L0058 19 11 NOCOMMON 0 0 L0058 19 12 DATA 3 1 L0058 19 13 EN-MIN EN-MAX DATA L0058 19 14 MEV MEV B*MEV L0058 19 15 6.844 18.3 1.06 L0058 19 16 ENDDATA 3 0 L0058 19 17 ENDSUBENT 16 0 L0058 1999999 SUBENT L0058020 20150127 L026L0058 20 1 BIB 4 7 L0058 20 2 REACTION ((93-NP-237(G,N)93-NP-236,,INT)+ L0058 20 3 (93-NP-237(G,N+P)92-U-235,,INT)) L0058 20 4 Fission neutron contribution is excluded. L0058 20 5 ERR-ANALYS No information. L0058 20 6 STATUS (DEP,L0058008) Data taken from TABLE 9 of article L0058 20 7 HISTORY (20150127A) Corrected by V.Varlamov: DATA and L0058 20 8 DATA-UNIT substituted. L0058 20 9 ENDBIB 7 0 L0058 20 10 NOCOMMON 0 0 L0058 20 11 DATA 3 1 L0058 20 12 EN-MIN EN-MAX DATA L0058 20 13 MEV MEV B*MEV L0058 20 14 6.628 18.3 1.17 L0058 20 15 ENDDATA 3 0 L0058 20 16 ENDSUBENT 15 0 L0058 2099999 SUBENT L0058021 20150127 L026L0058 21 1 BIB 4 9 L0058 21 2 REACTION ((93-NP-237(G,2N)93-NP-235,,INT)+ L0058 21 3 (93-NP-237(G,2N+P)92-U-234,,INT)) L0058 21 4 Threshold of the reaction (gamma,2n+p) is 16.7 MeV. L0058 21 5 Fission neutron contribution is excluded. L0058 21 6 ERR-ANALYS No information. L0058 21 7 STATUS (DEP,L0058009) Data taken from TABLE 9 of article. L0058 21 8 HISTORY (19950407A) REACTION corrected. L0058 21 9 (20150127A) Corrected by V.Varlamov: DATA and L0058 21 10 DATA-UNIT substituted, ERR-ANALYS. L0058 21 11 ENDBIB 9 0 L0058 21 12 NOCOMMON 0 0 L0058 21 13 DATA 3 1 L0058 21 14 EN-MIN EN-MAX DATA L0058 21 15 MEV MEV B*MEV L0058 21 16 12.31 18.3 0.35 L0058 21 17 ENDDATA 3 0 L0058 21 18 ENDSUBENT 17 0 L0058 2199999 SUBENT L0058022 20150127 L026L0058 22 1 BIB 3 3 L0058 22 2 REACTION (93-NP-237(G,F),,INT) L0058 22 3 ERR-ANALYS No information. L0058 22 4 STATUS (DEP,L0058010) Data taken from TABLES 9 and 2. L0058 22 5 ENDBIB 3 0 L0058 22 6 NOCOMMON 0 0 L0058 22 7 DATA 3 1 L0058 22 8 EN-MIN EN-MAX DATA L0058 22 9 MEV MEV B*MEV L0058 22 10 5.6 18.3 2.28 L0058 22 11 ENDDATA 3 0 L0058 22 12 ENDSUBENT 11 0 L0058 2299999 SUBENT L0058023 20150127 L026L0058 23 1 BIB 4 7 L0058 23 2 REACTION ((94-PU-239(G,N)94-PU-238,,INT)+ L0058 23 3 (94-PU-239(G,N+P)93-NP-237,,INT)) L0058 23 4 Fission neutron contribution is excluded. L0058 23 5 ERR-ANALYS No information. L0058 23 6 STATUS (DEP,L0058012) Data taken from TABLES 9 and 2. L0058 23 7 HISTORY (20150127A) Corrected by V.Varlamov: DATA and L0058 23 8 DATA-UNIT substituted. L0058 23 9 ENDBIB 7 0 L0058 23 10 NOCOMMON 0 0 L0058 23 11 DATA 3 1 L0058 23 12 EN-MIN EN-MAX DATA L0058 23 13 MEV MEV B*MEV L0058 23 14 5.647 17.8 0.63 L0058 23 15 ENDDATA 3 0 L0058 23 16 ENDSUBENT 15 0 L0058 2399999 SUBENT L0058024 20150127 L026L0058 24 1 BIB 4 6 L0058 24 2 REACTION (94-PU-239(G,2N)94-PU-237,,INT) L0058 24 3 Fission neutron contribution is excluded. L0058 24 4 ERR-ANALYS No information. L0058 24 5 STATUS (DEP,L0058013) Data taken from TABLES 9 and 2. L0058 24 6 HISTORY (20150127A) Corrected by V.Varlamov: DATA and L0058 24 7 DATA-UNIT substituted. L0058 24 8 ENDBIB 6 0 L0058 24 9 NOCOMMON 0 0 L0058 24 10 DATA 3 1 L0058 24 11 EN-MIN EN-MAX DATA L0058 24 12 MEV MEV B*MEV L0058 24 13 12.645 17.8 0.15 L0058 24 14 ENDDATA 3 0 L0058 24 15 ENDSUBENT 14 0 L0058 2499999 SUBENT L0058025 20150127 L026L0058 25 1 BIB 4 5 L0058 25 2 REACTION (94-PU-239(G,F),,INT) L0058 25 3 ERR-ANALYS No information. L0058 25 4 STATUS (DEP,L0058014) Data taken from TABLES 9 and 2. L0058 25 5 HISTORY (20150127A) Corrected by V.Varlamov: DATA and L0058 25 6 DATA-UNIT substituted. L0058 25 7 ENDBIB 5 0 L0058 25 8 NOCOMMON 0 0 L0058 25 9 DATA 3 1 L0058 25 10 EN-MIN EN-MAX DATA L0058 25 11 MEV MEV B*MEV L0058 25 12 5.8 17.8 0.215 L0058 25 13 ENDDATA 3 0 L0058 25 14 ENDSUBENT 13 0 L0058 2599999 SUBENT L0058026 20150127 L026L0058 26 1 BIB 5 11 L0058 26 2 REACTION (92-U-233(G,X)0-NN-1,UNW,SIG) L0058 26 3 The sum: (G,N)+(G,N+P)+(G,2N)+(G,F). L0058 26 4 SAMPLE (92-U-233,ENR=0.974) L0058 26 5 2 samples, 40.31 and 101.06 gram metal disks in L0058 26 6 brass can, 1.91 cm diam., 97.46% 233U. L0058 26 7 ERR-ANALYS (DATA-ERR) Uncertainties for total photonuclear cross L0058 26 8 sections computed by adding in quadrature those for L0058 26 9 the partial cross sections. L0058 26 10 STATUS (CURVE) Data from Fig 4 (a). L0058 26 11 HISTORY (20150127A) Corrected by V.Varlamov: REL-REF deleted, L0058 26 12 SAMPLE, STATUS, ERR-ANALYS, DATA substituted. L0058 26 13 ENDBIB 11 0 L0058 26 14 NOCOMMON 0 0 L0058 26 15 DATA 3 27 L0058 26 16 EN DATA DATA-ERR L0058 26 17 MEV MB MB L0058 26 18 5.06 10.54 0.7 L0058 26 19 5.56 12.59 0.84 L0058 26 20 6.08 15.66 1.04 L0058 26 21 6.52 21.73 1.44 L0058 26 22 7.05 30.83 2.05 L0058 26 23 7.49 38.91 2.58 L0058 26 24 7.95 54.03 3.59 L0058 26 25 8.49 61.11 4.06 L0058 26 26 8.95 91.31 6.06 L0058 26 27 9.49 131.6 8.74 L0058 26 28 9.95 198.90 4.89 L0058 26 29 10.49 298.64 5.43 L0058 26 30 10.96 380.00 3.80 L0058 26 31 11.45 402.95 8.17 L0058 26 32 11.96 409.95 3.26 L0058 26 33 12.44 428.30 6.52 L0058 26 34 12.91 467.29 10.86 L0058 26 35 13.42 461.54 8.09 L0058 26 36 13.9 445.25 8.23 L0058 26 37 14.41 369.34 9.29 L0058 26 38 14.87 350.22 6.03 L0058 26 39 15.39 293.21 8.95 L0058 26 40 15.84 263.24 7.06 L0058 26 41 16.36 241.63 3.26 L0058 26 42 16.81 179.18 7.33 L0058 26 43 17.32 180.98 7.06 L0058 26 44 17.76 185.6 12.33 L0058 26 45 ENDDATA 29 0 L0058 26 46 ENDSUBENT 45 0 L0058 2699999 SUBENT L0058027 20150127 L026L0058 27 1 BIB 5 13 L0058 27 2 REACTION (92-U-234(G,X)0-NN-1,UNW,SIG) L0058 27 3 The sum: (G,N)+(G,N+P)+(G,2N)+(G,F). L0058 27 4 SAMPLE (92-U-234,ENR=0.9984) L0058 27 5 (92-U-234,ENR=0.9978) L0058 27 6 2 samples, oxide powder in lucite cylinder, 2.54 cm L0058 27 7 diam.: 3.325 grams (99.84% 234U) and 12.525 grams L0058 27 8 (99.78% 234U). L0058 27 9 ERR-ANALYS (DATA-ERR) Uncertainties for total photonuclear cross L0058 27 10 sections computed by adding in quadrature those for L0058 27 11 the partial cross sections. L0058 27 12 STATUS (CURVE) Data from Fig 5 (a). L0058 27 13 HISTORY (20150127A) Corrected by V.Varlamov: REL-REF deleted, L0058 27 14 SAMPLE, STATUS, DATA-ERR, ERR-ANALYS. L0058 27 15 ENDBIB 13 0 L0058 27 16 NOCOMMON 0 0 L0058 27 17 DATA 3 27 L0058 27 18 EN DATA DATA-ERR L0058 27 19 MEV MB MB L0058 27 20 6.96 87.81 44.46 L0058 27 21 7.46 75.25 35.33 L0058 27 22 7.94 167.8 37.35 L0058 27 23 8.46 119.8 37.38 L0058 27 24 8.94 155.8 36.36 L0058 27 25 9.43 138.2 32.35 L0058 27 26 9.9 208.5 27.91 L0058 27 27 10.42 361.5 19.19 L0058 27 28 10.94 483.3 10.07 L0058 27 29 11.41 481.9 22.22 L0058 27 30 11.9 490.5 21.18 L0058 27 31 12.43 455.7 14.12 L0058 27 32 12.78 441.3 7.07 L0058 27 33 12.88 379.6 25.29 L0058 27 34 13.01 468.3 8.11 L0058 27 35 13.25 474.2 9.09 L0058 27 36 13.43 417.5 24.24 L0058 27 37 13.56 460.8 10.11 L0058 27 38 13.86 453.5 20.18 L0058 27 39 14.39 474.2 19.2 L0058 27 40 14.84 428.4 19.13 L0058 27 41 15.39 339.0 18.18 L0058 27 42 15.82 246.7 24.25 L0058 27 43 16.28 212.9 19.16 L0058 27 44 16.8 205.4 14.15 L0058 27 45 17.77 185.4 24.25 L0058 27 46 18.25 168.8 17.17 L0058 27 47 ENDDATA 29 0 L0058 27 48 ENDSUBENT 47 0 L0058 2799999 SUBENT L0058028 20150127 L026L0058 28 1 BIB 5 16 L0058 28 2 REACTION (94-PU-239(G,X)0-NN-1,UNW,SIG) L0058 28 3 The sum: (G,N)+(G,N+P)+(G,2N)+(G,F). L0058 28 4 SAMPLE (94-PU-239,ENR=0.9767) L0058 28 5 (94-PU-239,ENR=0.9992) L0058 28 6 2 samples: L0058 28 7 - metal disk in nickel can, 2.29 cm diam., 4.98 L0058 28 8 grams, 97.67% 239Pu, L0058 28 9 - metal cube in steel can, 1.25 cm edge, 29.91 L0058 28 10 grams, 99.92% 239Pu. L0058 28 11 ERR-ANALYS (DATA-ERR) Uncertainties for total photonuclear cross L0058 28 12 sections computed by adding in quadrature those for L0058 28 13 the partial cross sections. L0058 28 14 STATUS (CURVE) Data from Fig. 7 (a). L0058 28 15 HISTORY (20150127A) Corrected by V.Varlamov: REL-REF deleted, L0058 28 16 SAMPLE, STATUS, ERR-ANALYS, DATA-ERR, L0058 28 17 DATA substituted. L0058 28 18 ENDBIB 16 0 L0058 28 19 NOCOMMON 0 0 L0058 28 20 DATA 3 31 L0058 28 21 EN DATA DATA-ERR L0058 28 22 MEV MB MB L0058 28 23 6.03 10.76 3.11 L0058 28 24 6.3 14.79 3.22 L0058 28 25 6.56 24.21 5.96 L0058 28 26 6.89 26.90 7.63 L0058 28 27 7.15 36.32 4.30 L0058 28 28 7.4 54.18 5.40 L0058 28 29 7.66 61.83 5.17 L0058 28 30 8.04 64.59 4.59 L0058 28 31 8.28 65.58 5.66 L0058 28 32 8.59 67.27 7.29 L0058 28 33 8.76 69.96 5.18 L0058 28 34 9.05 95.30 6.46 L0058 28 35 9.34 107.62 4.84 L0058 28 36 9.52 139.91 5.38 L0058 28 37 9.79 161.14 8.07 L0058 28 38 10.02 219.28 5.38 L0058 28 39 10.54 344.39 13.56 L0058 28 40 10.97 398.82 8.61 L0058 28 41 11.49 484.30 16.45 L0058 28 42 11.99 484.19 14.53 L0058 28 43 12.36 446.64 10.71 L0058 28 44 12.93 435.87 26.49 L0058 28 45 13.45 445.67 26.59 L0058 28 46 13.96 467.02 14.59 L0058 28 47 14.4 441.26 21.52 L0058 28 48 14.88 323.45 32.29 L0058 28 49 15.4 252.19 18.83 L0058 28 50 15.84 152.19 24.22 L0058 28 51 16.37 172.20 26.91 L0058 28 52 16.88 215.60 13.45 L0058 28 53 17.83 166.82 16.14 L0058 28 54 ENDDATA 33 0 L0058 28 55 ENDSUBENT 54 0 L0058 2899999 SUBENT L0058029 20150127 L026L0058 29 1 BIB 5 8 L0058 29 2 REACTION (92-U-233(G,F),PR,NU) L0058 29 3 SAMPLE (92-U-233,ENR=0.974) L0058 29 4 2 samples, 40.31 and 101.06 gram metal disks in L0058 29 5 brass can, 1.91 cm diam., 97.46% 233U. L0058 29 6 ERR-ANALYS (ERR-S) Statistical errors. L0058 29 7 STATUS (CURVE) Data from Fig.2(a). L0058 29 8 HISTORY (20150127A) Corrected by V.Varlamov: SAMPLE, STATUS, L0058 29 9 ERR-ANALYS. L0058 29 9 L0058 29 10 ENDBIB 8 0 L0058 29 11 NOCOMMON 0 0 L0058 29 12 DATA 3 17 L0058 29 13 EN DATA ERR-S L0058 29 14 MEV PRT/FIS PRT/FIS L0058 29 15 8.205 2.451 0.082 L0058 29 16 9.470 2.803 0.117 L0058 29 17 9.910 2.767 0.117 L0058 29 18 10.378 2.908 0.094 L0058 29 19 10.873 3.061 0.059 L0058 29 20 11.368 3.342 0.094 L0058 29 21 11.835 3.178 0.082 L0058 29 22 12.276 3.471 0.094 L0058 29 23 12.798 3.448 0.094 L0058 29 24 13.238 3.565 0.094 L0058 29 25 13.706 3.530 0.070 L0058 29 26 14.201 3.694 0.117 L0058 29 27 14.724 3.612 0.106 L0058 29 28 15.191 3.788 0.094 L0058 29 29 15.934 3.764 0.106 L0058 29 30 16.622 4.128 0.117 L0058 29 31 17.584 4.233 0.152 L0058 29 32 ENDDATA 19 0 L0058 29 33 ENDSUBENT 32 0 L0058 2999999 SUBENT L0058030 20150127 L026L0058 30 1 BIB 5 10 L0058 30 2 REACTION (92-U-234(G,F),PR,NU) L0058 30 3 SAMPLE (92-U-234,ENR=0.9984) L0058 30 4 (92-U-234,ENR=0.9978) L0058 30 5 2 samples, oxide powder in lucite cylinder, 2.54 cm L0058 30 6 diam.: 3.325 grams (99.84% 234U) and 12.525 grams L0058 30 7 (99.78% 234U). L0058 30 8 ERR-ANALYS (ERR-S) Statistical errors. L0058 30 9 STATUS (CURVE) Data from Fig.2(b). L0058 30 10 HISTORY (20150127A) Corrected by V.Varlamov: SAMPLE, STATUS, L0058 30 11 ERR-ANALYS. L0058 30 12 ENDBIB 10 0 L0058 30 13 NOCOMMON 0 0 L0058 30 14 DATA 3 21 L0058 30 15 EN DATA ERR-S L0058 30 16 MEV PRT/FIS PRT/FIS L0058 30 17 7.915 2.898 0.316 L0058 30 18 9.356 2.616 0.199 L0058 30 19 9.828 2.827 0.222 L0058 30 20 10.355 2.826 0.129 L0058 30 21 10.827 3.013 0.105 L0058 30 22 11.353 2.931 0.152 L0058 30 23 11.798 3.188 0.164 L0058 30 24 12.298 3.316 0.187 L0058 30 25 12.631 3.316 0.117 L0058 30 26 12.769 3.292 0.129 L0058 30 27 12.936 3.327 0.105 L0058 30 28 13.157 3.350 0.105 L0058 30 29 13.295 3.116 0.164 L0058 30 30 13.379 3.374 0.129 L0058 30 31 13.768 3.362 0.117 L0058 30 32 14.238 3.174 0.129 L0058 30 33 14.711 3.431 0.129 L0058 30 34 15.182 3.548 0.129 L0058 30 35 15.904 3.699 0.187 L0058 30 36 16.626 3.886 0.234 L0058 30 37 17.596 3.908 0.339 L0058 30 38 ENDDATA 23 0 L0058 30 39 ENDSUBENT 38 0 L0058 3099999 SUBENT L0058031 20150127 L026L0058 31 1 BIB 4 5 L0058 31 2 REACTION (93-NP-237(G,F),PR,NU) L0058 31 3 ERR-ANALYS (ERR-S) Statistical errors. L0058 31 4 STATUS (CURVE) Data from Fig.2(c). L0058 31 5 HISTORY (20150127A) Corrected by V.Varlamov: STATUS, L0058 31 6 ERR-ANALYS. L0058 31 7 ENDBIB 5 0 L0058 31 8 NOCOMMON 0 0 L0058 31 9 DATA 3 21 L0058 31 10 EN DATA ERR-S L0058 31 11 MEV PRT/FIS PRT/FIS L0058 31 12 7.452 2.792 0.247 L0058 31 13 8.390 2.888 0.306 L0058 31 14 9.384 2.901 0.341 L0058 31 15 9.852 3.161 0.235 L0058 31 16 10.347 3.373 0.212 L0058 31 17 10.815 3.539 0.106 L0058 31 18 11.311 3.716 0.153 L0058 31 19 11.808 3.693 0.153 L0058 31 20 12.250 3.694 0.094 L0058 31 21 12.748 3.659 0.141 L0058 31 22 13.213 4.166 0.200 L0058 31 23 13.710 4.225 0.141 L0058 31 24 14.180 4.226 0.212 L0058 31 25 14.675 4.415 0.235 L0058 31 26 15.118 4.322 0.177 L0058 31 27 15.608 5.205 0.424 L0058 31 28 16.085 4.323 0.318 L0058 31 29 16.557 4.030 0.224 L0058 31 30 17.052 4.325 0.400 L0058 31 31 17.515 5.067 0.447 L0058 31 32 18.016 4.632 0.941 L0058 31 33 ENDDATA 23 0 L0058 31 34 ENDSUBENT 33 0 L0058 3199999 SUBENT L0058032 20150127 L026L0058 32 1 BIB 5 12 L0058 32 2 REACTION (94-PU-239(G,F),PR,NU) L0058 32 3 SAMPLE (94-PU-239,ENR=0.9767) L0058 32 4 (94-PU-239,ENR=0.9992) L0058 32 5 2 samples: L0058 32 6 - metal disk in nickel can, 2.29 cm diam., 4.98 L0058 32 7 grams, 97.67% 239Pu, L0058 32 8 - metal cube in steel can, 1.25 cm edge, 29.91 L0058 32 9 grams, 99.92% 239Pu. L0058 32 10 ERR-ANALYS (ERR-S) Statistical errors. L0058 32 11 STATUS (CURVE) Data from Fig.2(d). L0058 32 12 HISTORY (20150127A) Corrected by V.Varlamov: SAMPLE, STATUS, L0058 32 13 ERR-ANALYS. L0058 32 14 ENDBIB 12 0 L0058 32 15 NOCOMMON 0 0 L0058 32 16 DATA 3 20 L0058 32 17 EN DATA ERR-S L0058 32 18 MEV PRT/FIS PRT/FIS L0058 32 19 7.120 2.892 0.143 L0058 32 20 7.692 3.078 0.198 L0058 32 21 7.929 3.507 0.176 L0058 32 22 8.136 3.419 0.165 L0058 32 23 8.448 3.550 0.165 L0058 32 24 8.786 3.539 0.242 L0058 32 25 9.146 3.219 0.154 L0058 32 26 9.384 3.747 0.209 L0058 32 27 9.666 3.339 0.187 L0058 32 28 9.899 3.317 0.154 L0058 32 29 10.397 3.976 0.231 L0058 32 30 10.836 3.722 0.088 L0058 32 31 11.329 3.766 0.077 L0058 32 32 11.820 3.523 0.154 L0058 32 33 12.315 3.852 0.121 L0058 32 34 12.810 4.093 0.154 L0058 32 35 13.540 4.544 0.198 L0058 32 36 14.476 4.762 0.264 L0058 32 37 15.251 4.387 0.253 L0058 32 38 16.188 4.792 0.297 L0058 32 39 ENDDATA 22 0 L0058 32 40 ENDSUBENT 39 0 L0058 3299999 SUBENT L0058033 20150127 L026L0058 33 1 BIB 5 9 L0058 33 2 REACTION (93-NP-237(G,X)0-NN-1,UNW,SIG) L0058 33 3 The sum: (G,N)+(G,N+P)+(G,2N)+(G,2N+P)+(G,F). L0058 33 4 SAMPLE Metal sample in brass cylinder, 2.86 cm diam., 45.62 L0058 33 5 grams, 100% 237Np. L0058 33 6 ERR-ANALYS (DATA-ERR) Uncertainties for total photonuclear cross L0058 33 7 sections computed by adding in quadrature those for L0058 33 8 the partial cross sections. L0058 33 9 STATUS (CURVE) Data from Fig. 6 (a). L0058 33 10 HISTORY (20150127A) Corrected by V.Varlamov: new SUBENT added. L0058 33 11 ENDBIB 9 0 L0058 33 12 NOCOMMON 0 0 L0058 33 13 DATA 3 27 L0058 33 14 EN DATA DATA-ERR L0058 33 15 MEV MB MB L0058 33 16 5.51 5.27 15.82 L0058 33 17 6.00 18.46 15.56 L0058 33 18 6.49 29.00 13.19 L0058 33 19 6.98 36.92 8.97 L0058 33 20 7.47 52.48 7.91 L0058 33 21 7.96 60.66 5.27 L0058 33 22 8.45 76.48 8.44 L0058 33 23 8.94 108.13 7.92 L0058 33 24 9.43 160.88 5.20 L0058 33 25 9.92 253.19 8.97 L0058 33 26 10.41 377.14 10.55 L0058 33 27 10.90 461.54 5.00 L0058 33 28 11.40 480.00 7.65 L0058 33 29 11.89 458.90 15.82 L0058 33 30 12.38 465.49 10.55 L0058 33 31 12.87 482.00 13.19 L0058 33 32 13.36 580.22 18.46 L0058 33 33 13.85 582.86 15.82 L0058 33 34 14.34 569.67 21.01 L0058 33 35 14.83 516.92 20.00 L0058 33 36 15.32 453.94 13.23 L0058 33 37 15.81 378.46 16.88 L0058 33 38 16.30 311.21 18.46 L0058 33 39 16.79 250.39 10.55 L0058 33 40 17.28 239.74 13.19 L0058 33 41 17.77 226.81 13.19 L0058 33 42 18.26 224.28 29.01 L0058 33 43 ENDDATA 29 0 L0058 33 44 ENDSUBENT 43 0 L0058 3399999 SUBENT L0058034 20150127 L026L0058 34 1 BIB 4 4 L0058 34 2 REACTION (92-U-233(G,X)0-NN-1,UNW,INT) L0058 34 3 ERR-ANALYS No information. L0058 34 4 STATUS (DEP,L0058026) Data taken from TABLES 9 and 2. L0058 34 5 HISTORY (20150127A) Corrected by V.Varlamov: new SUBENT added. L0058 34 6 ENDBIB 4 0 L0058 34 7 NOCOMMON 0 0 L0058 34 8 DATA 3 1 L0058 34 9 EN-MIN EN-MAX DATA L0058 34 10 MEV MEV B*MEV L0058 34 11 5.753 17.8 3.02 L0058 34 12 ENDDATA 3 0 L0058 34 13 ENDSUBENT 12 0 L0058 3499999 SUBENT L0058035 20150127 L026L0058 35 1 BIB 4 4 L0058 35 2 REACTION (92-U-234(G,X)0-NN-1,UNW,INT) L0058 35 3 ERR-ANALYS No information. L0058 35 4 STATUS (DEP,L0058027) Data taken from TABLES 9 and 2. L0058 35 5 HISTORY (20150127A) Corrected by V.Varlamov: new SUBENT added. L0058 35 6 ENDBIB 4 0 L0058 35 7 NOCOMMON 0 0 L0058 35 8 DATA 3 1 L0058 35 9 EN-MIN EN-MAX DATA L0058 35 10 MEV MEV B*MEV L0058 35 11 6.844 18.3 3.32 L0058 35 12 ENDDATA 3 0 L0058 35 13 ENDSUBENT 12 0 L0058 3599999 SUBENT L0058036 20150127 L026L0058 36 1 BIB 4 4 L0058 36 2 REACTION (93-NP-237(G,X)0-NN-1,UNW,INT) L0058 36 3 ERR-ANALYS No information. L0058 36 4 STATUS (DEP,L0058029) Data taken from TABLES 9 and 2. L0058 36 5 HISTORY (20150127A) Corrected by V.Varlamov: new SUBENT added. L0058 36 6 ENDBIB 4 0 L0058 36 7 NOCOMMON 0 0 L0058 36 8 DATA 3 1 L0058 36 9 EN-MIN EN-MAX DATA L0058 36 10 MEV MEV B*MEV L0058 36 11 6.628 18.3 3.80 L0058 36 12 ENDDATA 3 0 L0058 36 13 ENDSUBENT 12 0 L0058 3699999 SUBENT L0058037 20150127 L026L0058 37 1 BIB 4 4 L0058 37 2 REACTION (94-PU-239(G,X)0-NN-1,UNW,INT) L0058 37 3 ERR-ANALYS No information. L0058 37 4 STATUS (DEP,L0058028) Data taken from TABLES 9 and 2. L0058 37 5 HISTORY (20150127A) Corrected by V.Varlamov: new SUBENT added. L0058 37 6 ENDBIB 4 0 L0058 37 7 NOCOMMON 0 0 L0058 37 8 DATA 3 1 L0058 37 9 EN-MIN EN-MAX DATA L0058 37 10 MEV MEV B*MEV L0058 37 11 5.647 17.8 2.93 L0058 37 12 ENDDATA 3 0 L0058 37 13 ENDSUBENT 12 0 L0058 3799999 ENDENTRY 37 0 L005899999999