ENTRY 20070 20230515 231720070 0 1 SUBENT 20070001 20230515 231720070 1 1 BIB 16 61 20070 1 2 TITLE Cross sections for high-energy gamma-transitions from 20070 1 3 MeV neutron capture in Pb-206 20070 1 4 AUTHOR (I.Bergqvist, B.Lundberg, L.Nilsson) 20070 1 5 REFERENCE (J,NP/A,153,553,1970) 20070 1 6 (W,NILSSON,197010) Letter 27/10/70 with data table. 20070 1 7 INSTITUTE (2SWDAE ,2SWDFOA) 20070 1 8 FACILITY (VDG,2SWDAE ) 5.5 MeV Van de Graaff accelerator. 20070 1 9 INC-SOURCE (D-D) D(d-n)-reaction, gas target, 20070 1 10 in the energy range 4.5 to 8.5 MeV. 20070 1 11 (P-T) T(p,n)-reaction, gas and absorbed target, 20070 1 12 in the energy range below 4.5 MeV. 20070 1 13 SAMPLE Radiogenic lead. 20070 1 14 Pb-204 0.08%, Pb-206 88.38%, 20070 1 15 Pb-207 8.57%, Pb-208 29,7%. 20070 1 16 A bismuth sample of same size as the Pb-206 was used 20070 1 17 to determine the background. 20070 1 18 METHOD Direct detection. 20070 1 19 (TOF) Distance sample to gamma-detector is 0.9 m. and 20070 1 20 1.4 m. in two runs respectively. 20070 1 21 DETECTOR (NAICR) Large NaI(Tl) detector, 22.6 cm in diameter 20070 1 22 and 20.8 cm long. 20070 1 23 Natrium-iodide detector placed at 90 degrees to the 20070 1 24 incident ion beam. 20070 1 25 (SCIN) Plastic scintillation detector for monitoring 20070 1 26 neutron yield under 140 degrees by time-of-flight 20070 1 27 techniques. 20070 1 28 Plastic scintillation detector placed at 140 degrees 20070 1 29 to the incident ion beam. 20070 1 30 A 4096-channel analyser was used in two-parameter mode20070 1 31 with flight time recorded in 16 channels and gamma-ray20070 1 32 pulse height in 256 channels. 20070 1 33 ANALYSIS The pulse-height spectra were unfolded by the detector20070 1 34 response functions. The pulse-height distribution 20070 1 35 obtained from the C-12(n,gamma)C-13 reaction at 20070 1 36 E(n) = 8.50 MeV was compared with the response 20070 1 37 function at 12.77 MeV. 20070 1 38 REL-REF (M,20065001,I.Bergqvist+,J,NP/A,120,161,1968) 20070 1 39 (I,,J.S.Bame Jr+,J,RSI,28,997,1957) 20070 1 40 MONITOR T(p,n) neutron production cross-section. 20070 1 41 For neutron energies less than about 1 MeV at 140 deg.20070 1 42 (Corresponding to less than about 4 MeV at 0 degrees),20070 1 43 the product of the integrated target current, 20070 1 44 the target gas pressure and the neutron production 20070 1 45 cross-section was used to normalize to the neutron 20070 1 46 yield at higher energies, as the time-of-flight 20070 1 47 monitor could not Be used in that case. 20070 1 48 (1-H-1(N,EL)1-H-1,,SIG) 20070 1 49 For higher energies, the plastic 20070 1 50 scintillator placed at 140 degrees to the incident 20070 1 51 beam was used. This counter was calibrated against a 20070 1 52 polyethylene count. of Los Alamos design (see REL-REF)20070 1 53 COMMENT The results are in agreement with the prediction of 20070 1 54 semi-direct capture theory. 20070 1 55 CORRECTION The results are corrected for neutron and gamma-ray 20070 1 56 attenuation and for neutron multiple scattering. 20070 1 57 ERR-ANALYS (DATA-ERR) No details. Only the errors for unfolding 20070 1 58 of spectra were discussed. 20070 1 59 HISTORY (19701105C) 20070 1 60 (20190925A) SD:Updated to new date formats,lower case. 20070 1 61 Subents 002-004 merged. 20070 1 62 (20230515A) SD: Correction in Subent 002. 20070 1 63 ENDBIB 61 0 20070 1 64 NOCOMMON 0 0 20070 1 65 ENDSUBENT 64 0 20070 199999 SUBENT 20070002 20230515 231720070 2 1 BIB 4 13 20070 2 2 REACTION (82-PB-206(N,G)82-PB-207,PAR,SIG) 20070 2 3 COMMENT The partial neutron capture cross section of high- 20070 2 4 energy gamma transitions in the Pb-206(n,g)Pb-207 to 20070 2 5 individual single particle states in Pb-207 such as 20070 2 6 0.00 MeV --- (p(1/2)), 20070 2 7 0.57 MeV + 0.90 MeV--- (F(5/2)-) + (p(3/2)-), 20070 2 8 2.74 MeV --- (g(9/2)), 20070 2 9 are given. 20070 2 10 STATUS (TABLE) Data from L.Nillson 27/10/1970. Data given on 20070 2 11 fig. 5 of Nucl.Phys.,A153(1970)553 20070 2 12 HISTORY (20190925A) SD: Data from Subents 003, 004 added. 20070 2 13 (20230515A) SD: COMMON deleted (value presented in 20070 2 14 col. of DATA). 20070 2 15 ENDBIB 13 0 20070 2 16 NOCOMMON 0 0 20070 2 17 DATA 6 25 20070 2 18 E-LVL E-LVL EN DATA DATA-ERR DATA-MAX 20070 2 19 MEV MEV MEV B B B 20070 2 20 0. 1.58 4.830E-04 1.20E-04 20070 2 21 0. 2.39 4.790E-04 1.20E-04 20070 2 22 0. 3.19 1.910E-04 4.80E-05 20070 2 23 0. 3.99 2.860E-04 7.20E-05 20070 2 24 0. 4.08 3.660E-04 9.20E-05 20070 2 25 0. 4.45 2.690E-04 6.70E-05 20070 2 26 0. 4.56 2.730E-04 6.80E-05 20070 2 27 0. 5.38 1.730E-04 4.30E-05 20070 2 28 0. 5.44 2.060E-04 5.20E-05 20070 2 29 0. 6.46 1.600E-04 4.00E-05 20070 2 30 0. 6.50 1.760E-04 4.40E-05 20070 2 31 0. 7.46 2.030E-04 5.10E-05 20070 2 32 0. 7.49 1.940E-04 4.90E-05 20070 2 33 0. 8.43 1.230E-04 3.10E-05 20070 2 34 0. 8.45 1.120E-04 2.80E-05 20070 2 35 0.9 0.57 4.08 2.970E-04 8.90E-05 20070 2 36 0.9 0.57 4.45 4.020E-04 1.20E-04 20070 2 37 0.9 0.57 5.38 3.040E-04 9.10E-05 20070 2 38 0.9 0.57 6.46 1.770E-04 5.30E-05 20070 2 39 0.9 0.57 7.46 1.240E-04 3.70E-05 20070 2 40 0.9 0.57 8.43 8.300E-05 2.50E-05 20070 2 41 2.74 5.38 1.60E-0420070 2 42 2.74 6.46 2.32E-04 4.70E-05 20070 2 43 2.74 7.46 3.85E-04 7.70E-05 20070 2 44 2.74 8.43 5.80E-04 1.16E-04 20070 2 45 ENDDATA 27 0 20070 2 46 ENDSUBENT 45 0 20070 299999 NOSUBENT 20070003 20190925 228320070 3 1 NOSUBENT 20070004 20190925 228320070 4 1 ENDENTRY 4 0 2007099999999