ENTRY M0785 20100225 M052M078500000001 SUBENT M0785001 20100225 M052M078500100001 BIB 14 80 M078500100002 TITLE Measurement of neutron photoproduction cross sections M078500100003 for 232Th and 238U using capture gamma rays. M078500100004 AUTHOR (O.L.Goncalez,L.P.Geraldo,R.Semmler) M078500100005 REFERENCE (J,NSE,132,135,1999) M078500100006 INSTITUTE (3BZLIPE) M078500100007 FACILITY (REAC,3BZLIPE) IPEN-IAE-R12-MW research reactor. M078500100008 INC-SOURCE (MPH) 30 neutron capture gamma rays with M078500100009 high-resolution in energy (4 to 20 eV) gamma-rays M078500100010 with discrete energies from 5.61 to 10.83 MeV: M078500100011 Capture target Gamma-ray energy, keV M078500100012 ---------------------------------------------------- M078500100013 Dy 5607.75 M078500100014 Hf 5723.50 M078500100015 In 5891.90 M078500100016 Hg 5966.20 M078500100017 Y 6080.49 M078500100018 Er 6228.23 M078500100019 Na 6395.40 M078500100020 Ca 6419.90 M078500100021 Nd 6501.70 M078500100022 V 6517.26 M078500100023 Gd 6748.70 M078500100024 Ti 6760.13 M078500100025 Yb 6779.80 M078500100026 Be 6809.41 M078500100027 As 7019.45 M078500100028 Sm 7214.20 M078500100029 Mn 7243.79 M078500100030 Pb 7367.70 M078500100031 Cl 7413.80 M078500100032 Se 7418.47 M078500100033 Fe 7631.13 M078500100034 Al 7723.85 M078500100035 K 7770.22 M078500100036 S 7800.00 M078500100037 Zn 7863.30 M078500100038 Cu 7914.50 M078500100039 Cd 8484.80 M078500100040 Ni 8998.80 M078500100041 Cr 9720.30 M078500100042 N 10829.18 M078500100043 SAMPLE Samples of 232Th and 238U were built in the form of M078500100044 pellets, using 17.76 g of (U-3)(O-8) depleted to 0.34 M078500100045 % in 235U isotope and 19.93 g of natural Th(O-2). M078500100046 These samples were packed inside an Al cylinder, 2.54 M078500100047 cm internal diameter and 2.5 cm high. M078500100048 DETECTOR (PROPC) 4PI sr long-counter detector system with high M078500100049 efficiency formed by 36 3He proportional detectors M078500100050 distributed into three concentric rings inside a M078500100051 polyethylene cube where neutrons are slowed down. M078500100052 METHOD (EXTB,SITA) M078500100053 ANALYSIS (UNFLD) The method of unfolding of cross section data M078500100054 for definite gamma-lines from those obtained for M078500100055 composition of all gamma-lines used employed the M078500100056 1Special iterative method. M078500100057 2The least-square method. M078500100058 ERR-ANALYS (ERR-T) The overall uncertainties were estimated M078500100059 by summing in quadrature all following components: M078500100060 Error Sources Range (%) M078500100061 --------------------------------------------------- M078500100062 (DATA-ERR1) Neutron counting random error M078500100063 (maximim value) .38 - 30.32 M078500100064 (DATA-ERR2) Gamma-ray counting random error M078500100065 (maximum value) 0.46 - 9.68 M078500100066 (ERR-1) Long-counter efficiency 1.8 M078500100067 (ERR-2) Gamma-ray intensity ratio 0.29 M078500100068 (ERR-3) Gamma-ray flux attenuation M078500100069 (maximum value) 1.19 - 7.8 M078500100070 (ERR-4) Ge(Li) calibration factor M078500100071 (maximum value) .84 - 3.51 M078500100072 COMMENT The compound neutron photoproduction cross section was M078500100073 measured for the gamma-ray spectrum produced by each M078500100074 capture target. Two methods to unfold the set of M078500100075 experimental data were proposed in order to obtain M078500100076 the differential cross sections at the main gamma M078500100077 line energies: the iterative and the least-square M078500100078 methods. M078500100079 STATUS (TABLE) Data from the Tables III and IV were compiled M078500100080 at the Russia MSU SINP CDFE by V.Varlamov. M078500100081 HISTORY (20100225C) M078500100082 ENDBIB 80 0 M078500100083 COMMON 6 3 M078500100084 DATA-ERR1 DATA-ERR2 ERR-1 ERR-2 ERR-3 ERR-4 M078500100085 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT M078500100086 30.32 9.68 1.8 .29 7.8 3.51 M078500100087 ENDCOMMON 3 0 M078500100088 ENDSUBENT 87 0 M078500199999 SUBENT M0785002 20100225 M052M078500200001 BIB 2 3 M078500200002 REACTION 1(90-TH-232(G,N)90-TH-231,,SIG) M078500200003 2(90-TH-232(G,N)90-TH-231,,SIG) M078500200004 ERR-ANALYS (ERR-5) Sample mass 232Th - 0.05%. M078500200005 ENDBIB 3 0 M078500200006 COMMON 1 3 M078500200007 ERR-5 M078500200008 PER-CENT M078500200009 .05 M078500200010 ENDCOMMON 3 0 M078500200011 DATA 5 30 M078500200012 EN DATA 1ERR-T 1DATA 2ERR-T 2 M078500200013 KEV MB MB MB MB M078500200014 5607.75 1.06 .27 .5 1.4 M078500200015 5723.50 6.5 1.1 6.7 1.5 M078500200016 5891.90 13.2 1.6 13.4 2.8 M078500200017 5966.20 2.02 .46 1.9 .8 M078500200018 6080.49 5.52 .38 5.5 .4 M078500200019 6228.23 15.5 2.7 16.2 3. M078500200020 6395.40 22. 1.4 22.1 1.3 M078500200021 6419.90 15.0 1.1 15. 1. M078500200022 6501.70 59.3 4.5 59.8 4.5 M078500200023 6517.26 8.5 2.5 2.4 5.5 M078500200024 6748.70 36.9 3. 37.2 2.9 M078500200025 6760.13 44. 3.5 44.4 3.2 M078500200026 6779.80 43.2 5.5 43.2 8.8 M078500200027 6809.41 37.8 2.7 37.8 2.6 M078500200028 7019.45 29.4 5.8 32.2 6. M078500200029 7214.20 61.1 4.8 63.4 4.4 M078500200030 7243.79 44.3 5.6 41.7 6.1 M078500200031 7367.70 45.2 1.8 45.2 1.5 M078500200032 7413.80 38.3 7.8 41. 10. M078500200033 7418.47 76. 16. 97. 38. M078500200034 7631.13 55.8 6.7 58.1 6.1 M078500200035 7723.85 59.8 4.5 59.5 3.9 M078500200036 7770.22 64.1 5.7 63.3 5.1 M078500200037 7800.00 98.5 8.1 85. 38. M078500200038 7863.30 65.4 6.3 64.3 5.2 M078500200039 7914.50 66.8 7.2 66.2 6.5 M078500200040 8484.80 116. 18. 155. 87. M078500200041 8998.80 97. 10. 81. 35. M078500200042 9720.30 233. 32. 204. 65. M078500200043 10829.18 490. 40. 486. 40. M078500200044 ENDDATA 32 0 M078500200045 ENDSUBENT 44 0 M078500299999 SUBENT M0785003 20100225 M052M078500300001 BIB 2 3 M078500300002 REACTION 1(92-U-238(G,N)92-U-237,,SIG) M078500300003 2(92-U-238(G,N)92-U-237,,SIG) M078500300004 ERR-ANALYS (ERR-6) Sample mass 238U - 0.57%. M078500300005 ENDBIB 3 0 M078500300006 COMMON 1 3 M078500300007 ERR-6 M078500300008 PER-CENT M078500300009 .57 M078500300010 ENDCOMMON 3 0 M078500300011 DATA 5 30 M078500300012 EN DATA 1ERR-T 1DATA 2ERR-T 2 M078500300013 KEV MB MB MB MB M078500300014 5607.75 11.5 1.4 12. 2. M078500300015 5723.50 5.2 1.3 4.6 2.5 M078500300016 5891.90 52.5 4.7 52.8 4.9 M078500300017 5966.20 54.7 4.6 55.3 4.2 M078500300018 6080.49 21.9 1.3 21.9 1.2 M078500300019 6228.23 24.1 4.7 22.1 5.7 M078500300020 6395.40 36.4 2.2 36.3 2.1 M078500300021 6419.90 28.9 2.1 28.8 1.9 M078500300022 6501.70 49.8 4.1 50.2 4.5 M078500300023 6517.26 42. 6.9 51. 11. M078500300024 6748.70 30.3 3.2 30. 3.5 M078500300025 6760.13 64.3 5.4 63.7 4.8 M078500300026 6779.80 55.4 8.4 54. 15. M078500300027 6809.41 42.4 3.6 42.6 4.1 M078500300028 7019.45 52.1 9.6 46.1 9.3 M078500300029 7214.20 44. 5. 39.9 5.2 M078500300030 7243.79 85. 9.8 92. 11. M078500300031 7367.70 93.9 3.6 93.8 3.1 M078500300032 7413.80 49.6 9.4 47. 13. M078500300033 7418.47 48. 15. 39. 61. M078500300034 7631.13 65.1 8.5 63.9 9.3 M078500300035 7723.85 68.1 5.2 68.2 4.5 M078500300036 7770.22 61.1 6.1 63.5 6.5 M078500300037 7800.00 85.2 9. 85. 65. M078500300038 7863.30 104. 10. 106.4 8.5 M078500300039 7914.50 89.2 9.5 88.3 9.3 M078500300040 8484.80 140. 26. 131. 152. M078500300041 8998.80 177. 17. 181. 62. M078500300042 9720.30 312. 45. 318. 110. M078500300043 10829.18 695. 58. 694. 59. M078500300044 ENDDATA 32 0 M078500300045 ENDSUBENT 44 0 M078500399999 ENDENTRY 3 0 M078599999999