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