ENTRY 31528 20211005 32023152800000001 SUBENT 31528001 20211005 32023152800100001 BIB 12 57 3152800100002 TITLE Study of total discrete gamma radiation from aluminum 3152800100003 under 14.9 MeV neutron bombardment 3152800100004 REFERENCE (J,NSE,125,61,1997) 3152800100005 (J,NIM/A,371,504,1996) Some data repeated in tables 3152800100006 AUTHOR (Hongyu Zhou, Guangshun Huang) 3152800100007 INSTITUTE (3CPRBNU) 3152800100008 FACILITY (CCW,3CPRBNU) 300 keV deuteron beam 3152800100009 INC-SOURCE (D-T) 3152800100010 SAMPLE Solid cylindrical metal Al, size 3.020 x 3.044 cm, 3152800100011 weight 60.48 g, chemical purity better than 99.9% 3152800100012 METHOD Lifetime correction method, developed by authors to 3152800100013 completely separate delayed and prompt gamma 3152800100014 components. 3152800100015 (TOF) Pulsed fast neutron beam was used. 3152800100016 The time resolution of the whole pulsing system was 3152800100017 about 1 nsec. 3152800100018 The averaged pulsed deuteron beam current was 6-8 uA. 3152800100019 Neutron intensity was about 5.e+8 n/sec in 4pi. 3152800100020 TOF technique employed to reduce background of primary 3152800100021 and scattered neutrons. 3152800100022 (ASSOP) Absolute neutron flux was determined by 3152800100023 associated particle counting with a Si(Au) detector 3152800100024 at 135 degrees. 3152800100025 A NE-111 plastic scintillator was used for monitoring 3152800100026 neutron flux. 3152800100027 DETECTOR (GELI) Volume 110.7 cm3. 3152800100028 The resolution was 1.85 keV at 1.33 MeV. 3152800100029 The detector was positioned inside a main shield 3152800100030 composed of Fe, Pb, Cu, Li2CO3, and paraffin. 3152800100031 There was a secondary shield of Fe and W between main 3152800100032 shield and neutron target. This way the primary 3152800100033 neutron flux reaching the detector was reduced by 3152800100034 factor 10**-5. 3152800100035 CORRECTION Gamma production cross sections were corrected for the 3152800100036 following effects. In parentheses, typical values of 3152800100037 the correction in % as obtained for the 843.8 keV 3152800100038 line yield at 55 degrees. 3152800100039 - Intensity attenuation of neutrons in sample (14.3) 3152800100040 - Multiple scattering of elastically scattered 3152800100041 neutrons (3.3) 3152800100042 - Multiple scattering of inelastically scattered 3152800100043 neutrons (5.2) 3152800100044 - Absorption of gamma rays in sample (27.8) 3152800100045 - Intensity attenuation of neutrons in target substrate3152800100046 and cooling water (2.5) 3152800100047 - Solid-angle correction due to point approximation 3152800100048 for planar source (1.2) 3152800100049 ERR-ANALYS (ERR-T) Total error taken into account were the 3152800100050 following uncertainties: 3152800100051 - Counting statistics 30% 3152800100052 (ERR-1,,2.) Neutron flux determination (<2%)3152800100053 (ERR-2,1.5,2.5) Absolute detector efficiency (1.5-2.5%)3152800100054 (ERR-3,1.,3.) Correction factor (1-3%)3152800100055 HISTORY (20030312C) OS. 3152800100056 (20180122A) On. ERR-ANAYLYS updated. REFERENCE revised.3152800100057 (20211004A) VS. MONITOR in 001 moved to METHOD. 3152800100058 REACTION corrected in 007 and 010. 3152800100059 ENDBIB 57 0 3152800100060 COMMON 2 3 3152800100061 EN EN-RSL 3152800100062 MEV MEV 3152800100063 14.9 0.5 3152800100064 ENDCOMMON 3 0 3152800100065 ENDSUBENT 64 0 3152800199999 SUBENT 31528002 20030321 00003152800200001 BIB 4 5 3152800200002 REACTION (13-AL-27(N,A)11-NA-24,PAR,DA,G) 3152800200003 EN-SEC (E,G) 3152800200004 FLAG (1.) After beta decay of Na-24 (15.02 hrs), 3152800200005 gamma line from Mg-24 3152800200006 STATUS Data from Nucl.Sci.Eng.125(1997) 61, Table 3. 3152800200007 ENDBIB 5 0 3152800200008 NOCOMMON 0 0 3152800200009 DATA 7 14 3152800200010 E LVL-INI LVL-FIN ANG DATA ERR-T 3152800200011 FLAG 3152800200012 KEV KEV KEV ADEG MB/SR MB/SR 3152800200013 NO-DIM 3152800200014 91.0 563.3 472.3 55. 1.33 0.08 3152800200015 3152800200016 91.0 563.3 472.3 90. 1.00 0.08 3152800200017 3152800200018 91.0 563.3 472.3 140. 1.35 0.10 3152800200019 3152800200020 472.3 472.3 0. 55. 3.76 0.18 3152800200021 3152800200022 472.3 472.3 0. 90. 4.25 0.29 3152800200023 3152800200024 472.3 472.3 0. 140. 4.30 0.22 3152800200025 3152800200026 563.3 563.3 0. 55. 0.11 0.08 3152800200027 3152800200028 563.3 563.3 0. 90. 0.30 0.06 3152800200029 3152800200030 563.3 563.3 0. 140. 0.21 0.04 3152800200031 3152800200032 874.4 1346.7 472.3 55. 1.37 0.28 3152800200033 3152800200034 874.4 1346.7 472.3 90. 1.53 0.32 3152800200035 3152800200036 874.4 1346.7 472.3 140. 1.33 0.27 3152800200037 3152800200038 1368.6 1368.6 0. 55. 9.27 1.00 3152800200039 1. 3152800200040 2754.4 4122.8 1368.6 55. 8.85 1.00 3152800200041 1. 3152800200042 ENDDATA 32 0 3152800200043 ENDSUBENT 42 0 3152800299999 SUBENT 31528003 20030321 00003152800300001 BIB 4 5 3152800300002 REACTION (13-AL-27(N,P)12-MG-27,PAR,DA,G) 3152800300003 EN-SEC (E,G) 3152800300004 FLAG (1.) After beta decay of Mg-27 (9.46 m), 3152800300005 line from Al-27 3152800300006 STATUS Data from Nucl.Sci.Eng.125(1997) 61, Table 3. 3152800300007 ENDBIB 5 0 3152800300008 NOCOMMON 0 0 3152800300009 DATA 7 21 3152800300010 E LVL-INI LVL-FIN ANG DATA ERR-T 3152800300011 FLAG 3152800300012 KEV KEV KEV ADEG MB/SR MB/SR 3152800300013 NO-DIM 3152800300014 241.6 1939.9 1698.3 55. 0.33 0.08 3152800300015 3152800300016 241.6 1939.9 1698.3 90. 0.31 0.08 3152800300017 3152800300018 241.6 1939.9 1698.3 140. 0.31 0.08 3152800300019 3152800300020 843.8 843.8 0. 55. 3.72 0.18 3152800300021 1. 3152800300022 843.8 843.8 0. 90. 3.90 0.26 3152800300023 1. 3152800300024 843.8 843.8 0. 140. 3.78 0.19 3152800300025 1. 3152800300026 955.3 1939.9 984.6 55. 0.83 0.06 3152800300027 3152800300028 955.3 1939.9 984.6 90. 0.96 0.09 3152800300029 3152800300030 955.3 1939.9 984.6 140. 0.66 0.05 3152800300031 3152800300032 984.6 984.6 0. 55. 1.74 0.07 3152800300033 3152800300034 984.6 984.6 0. 90. 1.87 0.14 3152800300035 3152800300036 984.6 984.6 0. 140. 1.55 0.08 3152800300037 3152800300038 1014.5 1014.5 0. 55. 1.87 0.12 3152800300039 1. 3152800300040 1014.5 1014.5 0. 90. 1.73 0.17 3152800300041 1. 3152800300042 1014.5 1014.5 0. 140. 2.03 0.17 3152800300043 1. 3152800300044 1698.3 1698.3 0. 55. 2.00 0.40 3152800300045 3152800300046 1698.3 1698.3 0. 90. 2.08 0.43 3152800300047 3152800300048 1698.3 1698.3 0. 140. 1.69 0.28 3152800300049 3152800300050 1940. 3880.0 1939.9 55. 1.03 0.31 3152800300051 3152800300052 1940. 3880.0 1939.9 90. 1.17 0.59 3152800300053 3152800300054 1940. 3880.0 1939.9 140. 1.15 0.29 3152800300055 3152800300056 ENDDATA 46 0 3152800300057 ENDSUBENT 56 0 3152800399999 SUBENT 31528004 20030321 00003152800400001 BIB 3 3 3152800400002 REACTION (13-AL-27(N,2N)13-AL-26,PAR,DA,G) 3152800400003 EN-SEC (E,G) 3152800400004 STATUS Data from Nucl.Sci.Eng.125(1997) 61, Table 3. 3152800400005 ENDBIB 3 0 3152800400006 NOCOMMON 0 0 3152800400007 DATA 6 3 3152800400008 E LVL-INI LVL-FIN ANG DATA ERR-T 3152800400009 KEV KEV KEV ADEG MB/SR MB/SR 3152800400010 416.9 416.9 0. 55. 0.32 0.13 3152800400011 416.9 416.9 0. 90. 0.42 0.17 3152800400012 416.9 416.9 0. 140. 0.27 0.05 3152800400013 ENDDATA 5 0 3152800400014 ENDSUBENT 13 0 3152800499999 SUBENT 31528005 20030321 00003152800500001 BIB 3 3 3152800500002 REACTION (13-AL-27(N,N+A)11-NA-23,PAR,DA,G) 3152800500003 EN-SEC (E,G) 3152800500004 STATUS Data from Nucl.Sci.Eng.125(1997) 61, Table 3. 3152800500005 ENDBIB 3 0 3152800500006 NOCOMMON 0 0 3152800500007 DATA 6 3 3152800500008 E LVL-INI LVL-FIN ANG DATA ERR-T 3152800500009 KEV KEV KEV ADEG MB/SR MB/SR 3152800500010 439.9 439.9 0. 55. 0.54 0.04 3152800500011 439.9 439.9 0. 90. 0.51 0.05 3152800500012 439.9 439.9 0. 140. 0.53 0.08 3152800500013 ENDDATA 5 0 3152800500014 ENDSUBENT 13 0 3152800599999 SUBENT 31528006 20030321 00003152800600001 BIB 3 3 3152800600002 REACTION (13-AL-27(N,INL)13-AL-27,PAR,DA,G) 3152800600003 EN-SEC (E,G) 3152800600004 STATUS Data from Nucl.Sci.Eng.125(1997) 61, Table 3. 3152800600005 ENDBIB 3 0 3152800600006 NOCOMMON 0 0 3152800600007 DATA 6 21 3152800600008 E LVL-INI LVL-FIN ANG DATA ERR-T 3152800600009 KEV KEV KEV ADEG MB/SR MB/SR 3152800600010 792.1 3004.0 2211.9 55. 1.40 0.22 3152800600011 792.1 3004.0 2211.9 90. 1.52 0.14 3152800600012 792.1 3004.0 2211.9 140. 1.27 0.20 3152800600013 843.8 843.8 0. 55. 1.85 0.08 3152800600014 843.8 843.8 0. 90. 2.23 0.14 3152800600015 843.8 843.8 0. 140. 1.88 0.08 3152800600016 1014.5 1014.5 0. 55. 4.91 0.16 3152800600017 1014.5 1014.5 0. 90. 5.29 0.32 3152800600018 1014.5 1014.5 0. 140. 4.52 0.15 3152800600019 1719.5 2734.0 1014.5 55. 2.08 0.32 3152800600020 1719.5 2734.0 1014.5 90. 2.15 0.31 3152800600021 1719.5 2734.0 1014.5 140. 2.07 0.32 3152800600022 2211.9 2211.9 0. 55. 9.68 0.56 3152800600023 2211.9 2211.9 0. 90. 9.15 0.88 3152800600024 2211.9 2211.9 0. 140. 9.92 0.42 3152800600025 2298.4 4510.3 2211.9 55. 2.27 0.46 3152800600026 2298.4 4510.3 2211.9 90. 2.44 0.51 3152800600027 2298.4 4510.3 2211.9 140. 2.71 0.28 3152800600028 3004.0 3004.0 0. 55. 7.17 0.61 3152800600029 3004.0 3004.0 0. 90. 7.53 0.86 3152800600030 3004.0 3004.0 0. 140. 7.77 0.39 3152800600031 ENDDATA 23 0 3152800600032 ENDSUBENT 31 0 3152800699999 SUBENT 31528007 20211005 32023152800700001 BIB 3 4 3152800700002 REACTION (13-AL-27(N,X)12-MG-26,PAR,DA,G) 3152800700003 STATUS (TABLE) Data from Nucl.Sci.Eng.125(1997) 61, Table 3. 3152800700004 HISTORY (20211004A) VS. REACTION: right side deleted c.f. Memo 3152800700005 CP-D/0954. STATUS: code added. 3152800700006 ENDBIB 4 0 3152800700007 NOCOMMON 0 0 3152800700008 DATA 6 9 3152800700009 E LVL-INI LVL-FIN ANG DATA ERR-T 3152800700010 KEV KEV KEV ADEG MB/SR MB/SR 3152800700011 1002.6 3940.0 2938.4 55. 0.17 0.10 3152800700012 1002.6 3940.0 2938.4 90. 0.23 0.11 3152800700013 1002.6 3940.0 2938.4 140. 0.22 0.10 3152800700014 1129.7 2938.4 1808.7 55. 1.73 0.33 3152800700015 1129.7 2938.4 1808.7 90. 1.48 0.29 3152800700016 1129.7 2938.4 1808.7 140. 1.53 0.15 3152800700017 1808.7 1808.7 0. 55. 13.03 0.42 3152800700018 1808.7 1808.7 0. 90. 11.31 0.72 3152800700019 1808.7 1808.7 0. 140. 13.33 0.44 3152800700020 ENDDATA 11 0 3152800700021 ENDSUBENT 20 0 3152800799999 SUBENT 31528008 20030321 00003152800800001 BIB 4 4 3152800800002 REACTION (13-AL-27(N,X)0-G-0,PAR,DA,G) 3152800800003 COMMENT 1172.5 line was not assigned to a specific reaction 3152800800004 EN-SEC (E,G) 3152800800005 STATUS Data from Nucl.Sci.Eng.125(1997) 61, Table 3. 3152800800006 ENDBIB 4 0 3152800800007 NOCOMMON 0 0 3152800800008 DATA 4 3 3152800800009 E ANG DATA ERR-T 3152800800010 KEV ADEG MB/SR MB/SR 3152800800011 1172.5 55. 0.55 0.06 3152800800012 1172.5 90. 0.68 0.21 3152800800013 1172.5 140. 0.74 0.15 3152800800014 ENDDATA 5 0 3152800800015 ENDSUBENT 14 0 3152800899999 SUBENT 31528009 20030321 00003152800900001 BIB 3 7 3152800900002 REACTION (13-AL-27(N,A)11-NA-24,,SIG) 3152800900003 DECAY-DATA (11-NA-24,15.02HR,DG,1368.6,,DG,2754.4) 3152800900004 STATUS (DEP,31528002) Cross section was determined from 1368.83152800900005 and 2754.4 keV gamma line production (subentry 2) as a 3152800900006 consistency check. Data collection time was not 3152800900007 sufficient for a more precise result. 3152800900008 Data from Nucl.Sci.Eng.125(1997) 61, Table 4 3152800900009 ENDBIB 7 0 3152800900010 NOCOMMON 0 0 3152800900011 DATA 2 1 3152800900012 DATA ERR-T 3152800900013 MB MB 3152800900014 113.7 8.9 3152800900015 ENDDATA 3 0 3152800900016 ENDSUBENT 15 0 3152800999999 SUBENT 31528010 20211005 32023152801000001 BIB 4 7 3152801000002 REACTION (13-AL-27(N,A)11-NA-24-L,,SIG) 3152801000003 DECAY-DATA (11-NA-24-L,20.2MSEC,DG,472.3) 3152801000004 STATUS (DEP,31528002) Cross section was determined 3152801000005 from 472.3 keV gamma line production (subentry 2). 3152801000006 (TABLE) Data from Nucl.Sci.Eng.125(1997) 61, page 71. 3152801000007 HISTORY (20211004A) VS. SF4/DECAY-DATA: -M -> -L; 3152801000008 STATUS: code added. 3152801000009 ENDBIB 7 0 3152801000010 NOCOMMON 0 0 3152801000011 DATA 2 1 3152801000012 DATA ERR-T 3152801000013 MB MB 3152801000014 50.6 1.5 3152801000015 ENDDATA 3 0 3152801000016 ENDSUBENT 15 0 3152801099999 SUBENT 31528011 20030321 00003152801100001 BIB 3 5 3152801100002 REACTION (13-AL-27(N,P)12-MG-27,,SIG) 3152801100003 DECAY-DATA (12-MG-27,9.46MIN,DG,843.8,,DG,1014.5) 3152801100004 STATUS (DEP,31528003) Cross section was determined from 843.8 3152801100005 and 1014.5 keV gamma line production (subentry 3). 3152801100006 Data from Nucl.Sci.Eng.125(1997) 61, Table 4 3152801100007 ENDBIB 5 0 3152801100008 NOCOMMON 0 0 3152801100009 DATA 2 1 3152801100010 DATA ERR-T 3152801100011 MB MB 3152801100012 71.3 2.9 3152801100013 ENDDATA 3 0 3152801100014 ENDSUBENT 13 0 3152801199999 ENDENTRY 11 0 3152899999999