ENTRY 32616 20220826 32083261600000001
SUBENT 32616001 20220826 32083261600100001
BIB 11 43 3261600100002
TITLE Measurement of double differential cross sections of 3261600100003
secondary neutrons in the incident energy range 3261600100004
9-13 MeV 3261600100005
AUTHOR (Tang Hongqing, Qi Bujia, Zhou Zuying, Sa Jun, 3261600100006
Ke Zunjian, Sui Qingchang, Xia Haihong, Shen Guanren) 3261600100007
INSTITUTE (3CPRAEP) 3261600100008
REFERENCE (C,91BEIJIN,,32,1991) Graphs only 3261600100009
(C,94GATLIN,2,901,1994) graphs only 3261600100010
(J,CNP,14,147,1992) error information and table 3261600100011
(C,91JUELIC,,436,1991) DDX at 45 and 120 deg in figs. 3261600100012
FACILITY (VDGT,3CPRAEP) HI-13 tandem Van de Graaff 3261600100013
INC-SOURCE (D-D) 7 MeV pulsed deuteron beam impinges on a 3261600100014
deuterium gas target 3261600100015
SAMPLE Hollow cylinder of depleted uranium metal or bismuth 3261600100016
with an outside diameter of 3 cm, inside diameter of 3261600100017
1 cm and height of 3 cm. 3261600100018
DETECTOR (SCIN) The neutron detector is a liquid scintillator 3261600100019
with diameter of 10.4 cm and thickness of 5 cm. 3261600100020
METHOD -An abnormal fast neutron time-of-flight spectro- 3261600100021
meter is introduced in which the distance between 3261600100022
neutron source and sample is 220 cm, and distance 3261600100023
between sample and neutron detector is 70 cm. With 3261600100024
this spectrometer the two groups of neutrons induced 3261600100025
by monoenergetic and break-up neutrons from the d+d 3261600100026
reaction are well separated in the tof spectrum. 3261600100027
- Measurement with a normal TOF spectrometer. 3261600100028
STATUS (TABLE) Data was provided by authors through private 3261600100029
communication 3261600100030
HISTORY (19931105C) Compiled by Liang Qichang at CNDC 3261600100031
(19940615A) HW.-Reference replaced in subent 001, pre- 3261600100032
vious reference moved to subents 002-006. new subent 3261600100033
012 added. METHOD, ERR-ANALYS, MONITOR and COMMENT 3261600100034
moved to subents 002-011.- 3261600100035
(19960219U) HW.- Reference added. 3261600100036
(19970424A) Hw.- Outgoing particle sequence corrected 3261600100037
in subent 012.- 3261600100038
(20100219A) SD:Updated to new date formats,lower case. 3261600100039
Author's name corrected (Xiu Haiheng => Xiu Haihong); 3261600100040
one added (Shen Guanren); Title corrected 3261600100041
(20220826A) VT. AUTHOR: Ke Zunjuan->Ke Zunjian, 3261600100042
Xiu Haihong->Xia Haihong and 3261600100043
REFERENCE:(C,91JUELIC,,436,1991) and METHOD added and 3261600100044
revision in 002-006, 012 3261600100045
ENDBIB 43 0 3261600100046
COMMON 1 3 3261600100047
EN 3261600100048
MEV 3261600100049
9.6 3261600100050
ENDCOMMON 3 0 3261600100051
ENDSUBENT 50 0 3261600199999
SUBENT 32616002 20220826 32083261600200001
BIB 6 20 3261600200002
REACTION (92-U-238(N,X)0-NN-1,,DA/DE) 3261600200003
MONITOR (6-C-12(N,EL)6-C-12,,DA) 3261600200004
METHOD (TOF) An abnormal fast neutron time-of-flight spectro- 3261600200005
meter. 3261600200006
ERR-ANALYS Uncertainties estimated for double differential cross 3261600200007
section measurement of secondary neutrons 3261600200008
(ERR-T,5.4,11.2) Overall uncertainties 5.4-11.2% 3261600200009
(ERR-S) counting statistics 2-10% 3261600200010
(ERR-1) neutron detector efficiency 3% 3261600200011
(ERR-2) Monte-Carlo correction for multi-scattering 3261600200012
and neutron fluence attenuation 2% 3261600200013
(DATA-ERR) counting statistics for elastic 3261600200014
scattering of carbon 2% 3261600200015
(ERR-3) uncertainty of differential cross section 3261600200016
of elastic scattering of carbon 3% 3261600200017
COMMENT Double differential cross section for secondary 3261600200018
neutrons including the elastic scattering neutrons. 3261600200019
HISTORY (19940615U) HW.- Reference, METHOD, ERR-ANALYS, MONITOR3261600200020
and COMMENT added in BIB-section.- 3261600200021
(20220826U) VT. REFERENCE: J,CNP,14,147,1992 deleted 3261600200022
ENDBIB 20 0 3261600200023
COMMON 5 3 3261600200024
ANG ERR-1 ERR-2 ERR-3 DATA-ERR 3261600200025
ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3261600200026
45. 3. 2. 3. 2. 3261600200027
ENDCOMMON 3 0 3261600200028
DATA 3 21 3261600200029
E DATA ERR-S 3261600200030
MEV MB/SR/MEV PER-CENT 3261600200031
1.85 209.1 5.6 3261600200032
2.25 107.4 4.1 3261600200033
2.65 70.2000 4.1 3261600200034
3.05 59.3000 4.3 3261600200035
3.45 45.2000 4.9 3261600200036
3.85 33.4000 2.9 3261600200037
4.25 34.8000 3.0 3261600200038
4.65 28.6000 3.1 3261600200039
5.05 26.6000 3.4 3261600200040
5.45 18.3000 4.2 3261600200041
5.85 15.4000 4.5 3261600200042
6.25 10.3000 5.3 3261600200043
6.65 13.3000 5.2 3261600200044
7.05 11.3000 5.4 3261600200045
7.45 13.4000 5.2 3261600200046
7.85 9.5000 5.4 3261600200047
8.25 5.9000 7.7 3261600200048
8.65 11.0000 6.0 3261600200049
9.05 24.9000 3.6 3261600200050
9.45 385.2 1.0 3261600200051
9.85 55.9000 2.5 3261600200052
ENDDATA 23 0 3261600200053
ENDSUBENT 52 0 3261600299999
SUBENT 32616003 20220826 32083261600300001
BIB 6 20 3261600300002
REACTION (92-U-238(N,X)0-NN-1,,DA/DE) 3261600300003
MONITOR (6-C-12(N,EL)6-C-12,,DA) 3261600300004
METHOD (TOF) An abnormal fast neutron time-of-flight spectro- 3261600300005
meter. 3261600300006
ERR-ANALYS Uncertainties estimated for double differential cross 3261600300007
section measurement of secondary neutrons 3261600300008
(ERR-T,5.4,11.2) Overall uncertainties 5.4-11.2% 3261600300009
(ERR-S) counting statistics 2-10% 3261600300010
(ERR-1) neutron detector efficiency 3% 3261600300011
(ERR-2) Monte-Carlo correction for multi-scattering 3261600300012
and neutron fluence attenuation 2% 3261600300013
(DATA-ERR) counting statistics for elastic 3261600300014
scattering of carbon 2% 3261600300015
(ERR-3) uncertainty of differential cross section 3261600300016
of elastic scattering of carbon 3% 3261600300017
COMMENT Double differential cross section for secondary 3261600300018
neutrons including the elastic scattering neutrons. 3261600300019
HISTORY (19940615U) HW.- Reference, METHOD, ERR-ANALYS, MONITOR3261600300020
and COMMENT added in BIB-section.- 3261600300021
(20220826U) VT. REFERENCE: J,CNP,14,147,1992 deleted 3261600300022
ENDBIB 20 0 3261600300023
COMMON 5 3 3261600300024
ANG ERR-1 ERR-2 ERR-3 DATA-ERR 3261600300025
ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3261600300026
70. 3. 2. 3. 2. 3261600300027
ENDCOMMON 3 0 3261600300028
DATA 3 22 3261600300029
E DATA ERR-S 3261600300030
MEV MB/SR/MEV PER-CENT 3261600300031
1.850 198.2 3.400 3261600300032
2.250 101.7 2.400 3261600300033
2.650 77.8000 2.300 3261600300034
3.050 54.9000 2.500 3261600300035
3.450 49.4000 2.700 3261600300036
3.850 35.3000 2.300 3261600300037
4.250 31.1000 2.600 3261600300038
4.650 23.7000 2.800 3261600300039
5.050 17.5000 3.300 3261600300040
5.450 15.7000 3.500 3261600300041
5.850 12.4000 4.200 3261600300042
6.250 10.8000 4.200 3261600300043
6.650 7.4000 5.600 3261600300044
7.050 9.2000 5.000 3261600300045
7.450 8.3000 4.800 3261600300046
7.850 7.4000 5.000 3261600300047
8.250 7.4000 5.600 3261600300048
8.650 10.8000 4.700 3261600300049
9.050 27.2000 2.900 3261600300050
9.450 187.6 1.100 3261600300051
9.850 40.2000 2.500 3261600300052
10.25 0.4000 24.0 3261600300053
ENDDATA 24 0 3261600300054
ENDSUBENT 53 0 3261600399999
SUBENT 32616004 20220826 32083261600400001
BIB 6 20 3261600400002
REACTION (92-U-238(N,X)0-NN-1,,DA/DE) 3261600400003
MONITOR (6-C-12(N,EL)6-C-12,,DA) 3261600400004
METHOD (TOF) An abnormal fast neutron time-of-flight spectro- 3261600400005
meter. 3261600400006
ERR-ANALYS Uncertainties estimated for double differential cross 3261600400007
section measurement of secondary neutrons 3261600400008
(ERR-T,5.4,11.2) Overall uncertainties 5.4-11.2% 3261600400009
(ERR-S) counting statistics 2-10% 3261600400010
(ERR-1) neutron detector efficiency 3% 3261600400011
(ERR-2) Monte-Carlo correction for multi-scattering 3261600400012
and neutron fluence attenuation 2% 3261600400013
(DATA-ERR) counting statistics for elastic 3261600400014
scattering of carbon 2% 3261600400015
(ERR-3) uncertainty of differential cross section 3261600400016
of elastic scattering of carbon 3% 3261600400017
COMMENT Double differential cross section for secondary 3261600400018
neutrons including the elastic scattering neutrons. 3261600400019
HISTORY (19940615U) HW.- Reference, METHOD, ERR-ANALYS, MONITOR3261600400020
and COMMENT added in BIB-section.- 3261600400021
(20220826U) VT. REFERENCE: J,CNP,14,147,1992 deleted 3261600400022
ENDBIB 20 0 3261600400023
COMMON 5 3 3261600400024
ANG ERR-1 ERR-2 ERR-3 DATA-ERR 3261600400025
ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3261600400026
90. 3. 2. 3. 2. 3261600400027
ENDCOMMON 3 0 3261600400028
DATA 3 22 3261600400029
E DATA ERR-S 3261600400030
MEV MB/SR/MEV PER-CENT 3261600400031
1.850 144.7 7.300 3261600400032
2.250 90.1000 4.700 3261600400033
2.650 65.7000 4.500 3261600400034
3.050 50.5000 4.700 3261600400035
3.450 42.9000 5.300 3261600400036
3.850 29.2000 2.500 3261600400037
4.250 30.4000 2.700 3261600400038
4.650 20.7000 3.100 3261600400039
5.050 18.0000 3.300 3261600400040
5.450 15.6000 3.600 3261600400041
5.850 11.0000 4.100 3261600400042
6.250 7.6000 5.000 3261600400043
6.650 6.9000 5.800 3261600400044
7.050 6.9000 5.700 3261600400045
7.450 6.9000 5.300 3261600400046
7.850 5.5000 6.300 3261600400047
8.250 6.1000 6.400 3261600400048
8.650 5.6000 6.500 3261600400049
9.050 9.5000 4.700 3261600400050
9.450 55.0000 2.000 3261600400051
9.850 8.7000 5.100 3261600400052
10.25 1.1000 27.0 3261600400053
ENDDATA 24 0 3261600400054
ENDSUBENT 53 0 3261600499999
SUBENT 32616005 20220826 32083261600500001
BIB 6 20 3261600500002
REACTION (92-U-238(N,X)0-NN-1,,DA/DE) 3261600500003
MONITOR (6-C-12(N,EL)6-C-12,,DA) 3261600500004
METHOD (TOF) An abnormal fast neutron time-of-flight spectro- 3261600500005
meter. 3261600500006
ERR-ANALYS Uncertainties estimated for double differential cross 3261600500007
section measurement of secondary neutrons 3261600500008
(ERR-T,5.4,11.2) Overall uncertainties 5.4-11.2% 3261600500009
(ERR-S) counting statistics 2-10% 3261600500010
(ERR-1) neutron detector efficiency 3% 3261600500011
(ERR-2) Monte-Carlo correction for multi-scattering 3261600500012
and neutron fluence attenuation 2% 3261600500013
(DATA-ERR) counting statistics for elastic 3261600500014
scattering of carbon 2% 3261600500015
(ERR-3) uncertainty of differential cross section 3261600500016
of elastic scattering of carbon 3% 3261600500017
COMMENT Double differential cross section for secondary 3261600500018
neutrons including the elastic scattering neutrons. 3261600500019
HISTORY (19940615U) HW.- Reference, METHOD, ERR-ANALYS, MONITOR3261600500020
and COMMENT added in BIB-section.- 3261600500021
(20220826U) VT. REFERENCE: J,CNP,14,147,1992 deleted 3261600500022
ENDBIB 20 0 3261600500023
COMMON 5 3 3261600500024
ANG ERR-1 ERR-2 ERR-3 DATA-ERR 3261600500025
ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3261600500026
110. 3. 2. 3. 2. 3261600500027
ENDCOMMON 3 0 3261600500028
DATA 3 21 3261600500029
E DATA ERR-S 3261600500030
MEV MB/SR/MEV PER-CENT 3261600500031
1.85 174.9 3.1 3261600500032
2.25 79.0000 2.3 3261600500033
2.65 57.7000 2.9 3261600500034
3.05 43.2000 2.5 3261600500035
3.45 36.2000 2.8 3261600500036
3.85 26.2000 2.3 3261600500037
4.25 26.5000 2.7 3261600500038
4.65 18.0000 3.0 3261600500039
5.05 15.5000 3.4 3261600500040
5.45 10.6000 4.0 3261600500041
5.85 8.3000 4.3 3261600500042
6.25 8.3000 4.8 3261600500043
6.65 7.6000 5.1 3261600500044
7.05 6.4000 5.5 3261600500045
7.45 4.6000 6.1 3261600500046
7.85 4.2000 7.0 3261600500047
8.25 5.7000 6.3 3261600500048
8.65 3.7000 7.7 3261600500049
9.05 10.2000 4.4 3261600500050
9.45 49.5000 2.0 3261600500051
9.85 6.2000 5.8 3261600500052
ENDDATA 23 0 3261600500053
ENDSUBENT 52 0 3261600599999
SUBENT 32616006 20220826 32083261600600001
BIB 6 20 3261600600002
REACTION (92-U-238(N,X)0-NN-1,,DA/DE) 3261600600003
MONITOR (6-C-12(N,EL)6-C-12,,DA) 3261600600004
METHOD (TOF) An abnormal fast neutron time-of-flight spectro- 3261600600005
meter. 3261600600006
ERR-ANALYS Uncertainties estimated for double differential cross 3261600600007
section measurement of secondary neutrons 3261600600008
(ERR-T,5.4,11.2) Overall uncertainties 5.4-11.2% 3261600600009
(ERR-S) counting statistics 2-10% 3261600600010
(ERR-1) neutron detector efficiency 3% 3261600600011
(ERR-2) Monte-Carlo correction for multi-scattering 3261600600012
and neutron fluence attenuation 2% 3261600600013
(DATA-ERR) counting statistics for elastic 3261600600014
scattering of carbon 2% 3261600600015
(ERR-3) uncertainty of differential cross section 3261600600016
of elastic scattering of carbon 3% 3261600600017
COMMENT Double differential cross section for secondary 3261600600018
neutrons including the elastic scattering neutrons. 3261600600019
HISTORY (19940615U) HW.- Reference, METHOD, ERR-ANALYS, MONITOR3261600600020
and COMMENT added in BIB-section.- 3261600600021
(20220826U) VT. REFERENCE: J,CNP,14,147,1992 deleted 3261600600022
ENDBIB 20 0 3261600600023
COMMON 5 3 3261600600024
ANG ERR-1 ERR-2 ERR-3 DATA-ERR 3261600600025
ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3261600600026
120. 3. 2. 3. 2. 3261600600027
ENDCOMMON 3 0 3261600600028
DATA 3 22 3261600600029
E DATA ERR-S 3261600600030
MEV MB/SR/MEV PER-CENT 3261600600031
1.850 255.1 4.500 3261600600032
2.250 103.3 3.700 3261600600033
2.650 77.5000 3.700 3261600600034
3.050 51.7000 4.200 3261600600035
3.450 43.7000 4.600 3261600600036
3.850 32.8000 2.800 3261600600037
4.250 42.9000 2.700 3261600600038
4.650 29.6000 3.300 3261600600039
5.050 23.6000 3.500 3261600600040
5.450 15.8000 4.200 3261600600041
5.850 15.9000 4.200 3261600600042
6.250 19.3000 4.100 3261600600043
6.650 7.6000 6.100 3261600600044
7.050 8.1000 6.100 3261600600045
7.450 5.3000 7.200 3261600600046
7.850 8.1000 6.500 3261600600047
8.250 7.4000 7.000 3261600600048
8.650 2.0000 12.9 3261600600049
9.050 7.7000 6.500 3261600600050
9.450 29.8000 3.200 3261600600051
9.850 2.0000 12.3 3261600600052
10.25 0.4000 25.0 3261600600053
ENDDATA 24 0 3261600600054
ENDSUBENT 53 0 3261600699999
SUBENT 32616007 20100219 31473261600700001
BIB 6 24 3261600700002
REACTION (83-BI-209(N,X)0-NN-1,,DA/DE) 3261600700003
MONITOR (6-C-12(N,EL)6-C-12,,DA) 3261600700004
METHOD (TOF) An abnormal fast neutron time-of-flight spectro- 3261600700005
meter is introduced in which the distance between 3261600700006
neutron source and sample is 220 cm, and distance 3261600700007
between sample and neutron detector is 70 cm. With 3261600700008
this spectrometer the two groups of neutrons induced 3261600700009
by monoenergetic and break-up neutrons from the d+d 3261600700010
reaction are well separated in the tof spectrum. 3261600700011
ERR-ANALYS Uncertainties estimated for double differential cross 3261600700012
section measurement of secondary neutrons 3261600700013
(ERR-S) counting statistics 2-10% 3261600700014
(ERR-1) neutron detector efficiency 3% 3261600700015
(ERR-2) Monte-Carlo correction for multi-scattering 3261600700016
and neutron fluence attenuation 2% 3261600700017
(DATA-ERR) counting statistics for elastic 3261600700018
scattering of carbon 2% 3261600700019
(ERR-3) uncertainty of differential cross section 3261600700020
of elastic scattering of carbon 3% 3261600700021
(ERR-T,5.4,11.2) total 5.4-11.2% 3261600700022
COMMENT Double differential cross section for secondary 3261600700023
neutrons including the elastic scattering neutrons. 3261600700024
HISTORY (19940615U) HW.- Reference, METHOD, ERR-ANALYS, MONITOR3261600700025
and COMMENT added in BIB-section.- 3261600700026
ENDBIB 24 0 3261600700027
COMMON 5 3 3261600700028
ANG ERR-1 ERR-2 ERR-3 DATA-ERR 3261600700029
ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3261600700030
45. 3. 2. 3. 2. 3261600700031
ENDCOMMON 3 0 3261600700032
DATA 3 21 3261600700033
E DATA ERR-S 3261600700034
MEV MB/SR/MEV PER-CENT 3261600700035
1.85 134.8 5.600 3261600700036
2.25 71.1000 4.100 3261600700037
2.65 44.6000 4.200 3261600700038
3.05 38.0000 4.600 3261600700039
3.45 26.8000 5.400 3261600700040
3.85 22.0000 2.700 3261600700041
4.25 20.9000 2.800 3261600700042
4.65 26.6000 2.500 3261600700043
5.05 18.4000 3.000 3261600700044
5.45 18.7000 2.900 3261600700045
5.85 7.4000 3.900 3261600700046
6.25 2.8000 7.100 3261600700047
6.65 4.2000 4.900 3261600700048
7.05 15.4000 3.200 3261600700049
7.45 0.2000 38.0 3261600700050
7.85 2.5000 9.000 3261600700051
8.25 0.9000 12.7 3261600700052
8.65 4.9000 6.600 3261600700053
9.05 30.3000 2.400 3261600700054
9.45 467.6 0.700 3261600700055
9.85 68.9000 1.800 3261600700056
ENDDATA 23 0 3261600700057
ENDSUBENT 56 0 3261600799999
SUBENT 32616008 20100219 31473261600800001
BIB 6 24 3261600800002
REACTION (83-BI-209(N,X)0-NN-1,,DA/DE) 3261600800003
MONITOR (6-C-12(N,EL)6-C-12,,DA) 3261600800004
METHOD (TOF) An abnormal fast neutron time-of-flight spectro- 3261600800005
meter is introduced in which the distance between 3261600800006
neutron source and sample is 220 cm, and distance 3261600800007
between sample and neutron detector is 70 cm. With 3261600800008
this spectrometer the two groups of neutrons induced 3261600800009
by monoenergetic and break-up neutrons from the d+d 3261600800010
reaction are well separated in the tof spectrum. 3261600800011
ERR-ANALYS Uncertainties estimated for double differential cross 3261600800012
section measurement of secondary neutrons 3261600800013
(ERR-S) counting statistics 2-10% 3261600800014
(ERR-1) neutron detector efficiency 3% 3261600800015
(ERR-2) Monte-Carlo correction for multi-scattering 3261600800016
and neutron fluence attenuation 2% 3261600800017
(DATA-ERR) counting statistics for elastic 3261600800018
scattering of carbon 2% 3261600800019
(ERR-3) uncertainty of differential cross section 3261600800020
of elastic scattering of carbon 3% 3261600800021
(ERR-T,5.4,11.2) total 5.4-11.2% 3261600800022
COMMENT Double differential cross section for secondary 3261600800023
neutrons including the elastic scattering neutrons. 3261600800024
HISTORY (19940615U) HW.- Reference, METHOD, ERR-ANALYS, MONITOR3261600800025
and COMMENT added in BIB-section.- 3261600800026
ENDBIB 24 0 3261600800027
COMMON 5 3 3261600800028
ANG ERR-1 ERR-2 ERR-3 DATA-ERR 3261600800029
ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3261600800030
70. 3. 2. 3. 2. 3261600800031
ENDCOMMON 3 0 3261600800032
DATA 3 22 3261600800033
E DATA ERR-S 3261600800034
MEV MB/SR/MEV PER-CENT 3261600800035
1.850 179.0 4.600 3261600800036
2.250 82.0000 3.700 3261600800037
2.650 48.1000 3.900 3261600800038
3.050 37.8000 4.400 3261600800039
3.450 31.0000 3.800 3261600800040
3.850 15.1000 3.900 3261600800041
4.250 10.6000 4.100 3261600800042
4.650 6.3000 5.300 3261600800043
5.050 7.5000 5.200 3261600800044
5.450 9.9000 4.600 3261600800045
5.850 3.8000 8.300 3261600800046
6.250 3.6000 8.000 3261600800047
6.650 3.0000 6.400 3261600800048
7.050 4.7000 5.400 3261600800049
7.450 1.7000 13.2 3261600800050
7.850 1.8000 12.6 3261600800051
8.250 0.1000 83.0 3261600800052
8.650 3.6000 9.200 3261600800053
9.050 13.0000 4.700 3261600800054
9.450 152.0 1.400 3261600800055
9.850 41.4000 2.700 3261600800056
10.25 0.6000 23.0 3261600800057
ENDDATA 24 0 3261600800058
ENDSUBENT 57 0 3261600899999
SUBENT 32616009 20100219 31473261600900001
BIB 6 24 3261600900002
REACTION (83-BI-209(N,X)0-NN-1,,DA/DE) 3261600900003
MONITOR (6-C-12(N,EL)6-C-12,,DA) 3261600900004
METHOD (TOF) An abnormal fast neutron time-of-flight spectro- 3261600900005
meter is introduced in which the distance between 3261600900006
neutron source and sample is 220 cm, and distance 3261600900007
between sample and neutron detector is 70 cm. With 3261600900008
this spectrometer the two groups of neutrons induced 3261600900009
by monoenergetic and break-up neutrons from the d+d 3261600900010
reaction are well separated in the tof spectrum. 3261600900011
ERR-ANALYS Uncertainties estimated for double differential cross 3261600900012
section measurement of secondary neutrons 3261600900013
(ERR-S) counting statistics 2-10% 3261600900014
(ERR-1) neutron detector efficiency 3% 3261600900015
(ERR-2) Monte-Carlo correction for multi-scattering 3261600900016
and neutron fluence attenuation 2% 3261600900017
(DATA-ERR) counting statistics for elastic 3261600900018
scattering of carbon 2% 3261600900019
(ERR-3) uncertainty of differential cross section 3261600900020
of elastic scattering of carbon 3% 3261600900021
(ERR-T,5.4,11.2) total 5.4-11.2% 3261600900022
COMMENT Double differential cross section for secondary 3261600900023
neutrons including the elastic scattering neutrons. 3261600900024
HISTORY (19940615U) HW.- Reference, METHOD, ERR-ANALYS, MONITOR3261600900025
and COMMENT added in BIB-section.- 3261600900026
ENDBIB 24 0 3261600900027
COMMON 5 3 3261600900028
ANG ERR-1 ERR-2 ERR-3 DATA-ERR 3261600900029
ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3261600900030
90. 3. 2. 3. 2. 3261600900031
ENDCOMMON 3 0 3261600900032
DATA 3 22 3261600900033
E DATA ERR-S 3261600900034
MEV MB/SR/MEV PER-CENT 3261600900035
1.850 115.9 6.500 3261600900036
2.250 59.6000 4.900 3261600900037
2.650 38.8000 4.900 3261600900038
3.050 37.9000 4.800 3261600900039
3.450 17.6000 6.800 3261600900040
3.850 16.7000 2.800 3261600900041
4.250 15.8000 3.000 3261600900042
4.650 12.0000 3.400 3261600900043
5.050 4.1000 5.900 3261600900044
5.450 7.3000 4.100 3261600900045
5.850 4.5000 5.900 3261600900046
6.250 5.5000 4.800 3261600900047
6.650 3.6000 4.100 3261600900048
7.050 6.6000 3.400 3261600900049
7.450 0.1000 84.0 3261600900050
7.850 3.7000 6.900 3261600900051
8.250 2.1000 9.200 3261600900052
8.650 1.0000 12.2 3261600900053
9.050 22.7000 2.900 3261600900054
9.450 80.4000 1.500 3261600900055
9.850 17.9000 3.200 3261600900056
10.25 0.5000 18.0 3261600900057
ENDDATA 24 0 3261600900058
ENDSUBENT 57 0 3261600999999
SUBENT 32616010 20100219 31473261601000001
BIB 6 24 3261601000002
REACTION (83-BI-209(N,X)0-NN-1,,DA/DE) 3261601000003
MONITOR (6-C-12(N,EL)6-C-12,,DA) 3261601000004
METHOD (TOF) An abnormal fast neutron time-of-flight spectro- 3261601000005
meter is introduced in which the distance between 3261601000006
neutron source and sample is 220 cm, and distance 3261601000007
between sample and neutron detector is 70 cm. With 3261601000008
this spectrometer the two groups of neutrons induced 3261601000009
by monoenergetic and break-up neutrons from the d+d 3261601000010
reaction are well separated in the tof spectrum. 3261601000011
ERR-ANALYS Uncertainties estimated for double differential cross 3261601000012
section measurement of secondary neutrons 3261601000013
(ERR-S) counting statistics 2-10% 3261601000014
(ERR-1) neutron detector efficiency 3% 3261601000015
(ERR-2) Monte-Carlo correction for multi-scattering 3261601000016
and neutron fluence attenuation 2% 3261601000017
(DATA-ERR) counting statistics for elastic 3261601000018
scattering of carbon 2% 3261601000019
(ERR-3) uncertainty of differential cross section 3261601000020
of elastic scattering of carbon 3% 3261601000021
(ERR-T,5.4,11.2) total 5.4-11.2% 3261601000022
COMMENT Double differential cross section for secondary 3261601000023
neutrons including the elastic scattering neutrons. 3261601000024
HISTORY (19940615U) HW.- Reference, METHOD, ERR-ANALYS, MONITOR3261601000025
and COMMENT added in BIB-section.- 3261601000026
ENDBIB 24 0 3261601000027
COMMON 5 3 3261601000028
ANG ERR-1 ERR-2 ERR-3 DATA-ERR 3261601000029
ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3261601000030
110. 3. 2. 3. 2. 3261601000031
ENDCOMMON 3 0 3261601000032
DATA 3 21 3261601000033
E DATA ERR-S 3261601000034
MEV MB/SR/MEV PER-CENT 3261601000035
1.85 154.4 4.8000 3261601000036
2.25 42.2000 4.6000 3261601000037
2.65 33.7000 4.3000 3261601000038
3.05 23.7000 5.3000 3261601000039
3.45 20.1000 5.6000 3261601000040
3.85 14.5000 2.7000 3261601000041
4.25 11.3000 3.1000 3261601000042
4.65 9.2000 3.4000 3261601000043
5.05 8.3000 3.7000 3261601000044
5.45 5.0000 4.6000 3261601000045
5.85 3.0000 6.1000 3261601000046
6.25 2.3000 6.8000 3261601000047
6.65 1.2000 6.2000 3261601000048
7.05 2.7000 5.1000 3261601000049
7.45 1.5000 9.3000 3261601000050
7.85 0.9000 11.9000 3261601000051
8.25 0.1000 100.0 3261601000052
8.65 0.4000 21.0000 3261601000053
9.05 8.5000 4.2000 3261601000054
9.45 35.7000 2.0000 3261601000055
9.85 1.7000 9.3000 3261601000056
ENDDATA 23 0 3261601000057
ENDSUBENT 56 0 3261601099999
SUBENT 32616011 20100219 31473261601100001
BIB 6 24 3261601100002
REACTION (83-BI-209(N,X)0-NN-1,,DA/DE) 3261601100003
MONITOR (6-C-12(N,EL)6-C-12,,DA) 3261601100004
METHOD (TOF) An abnormal fast neutron time-of-flight spectro- 3261601100005
meter is introduced in which the distance between 3261601100006
neutron source and sample is 220 cm, and distance 3261601100007
between sample and neutron detector is 70 cm. With 3261601100008
this spectrometer the two groups of neutrons induced 3261601100009
by monoenergetic and break-up neutrons from the d+d 3261601100010
reaction are well separated in the tof spectrum. 3261601100011
ERR-ANALYS Uncertainties estimated for double differential cross 3261601100012
section measurement of secondary neutrons 3261601100013
(ERR-S) counting statistics 2-10% 3261601100014
(ERR-1) neutron detector efficiency 3% 3261601100015
(ERR-2) Monte-Carlo correction for multi-scattering 3261601100016
and neutron fluence attenuation 2% 3261601100017
(DATA-ERR) counting statistics for elastic 3261601100018
scattering of carbon 2% 3261601100019
(ERR-3) uncertainty of differential cross section 3261601100020
of elastic scattering of carbon 3% 3261601100021
(ERR-T,5.4,11.2) total 5.4-11.2% 3261601100022
COMMENT Double differential cross section for secondary 3261601100023
neutrons including the elastic scattering neutrons. 3261601100024
HISTORY (19940615U) HW.- Reference, METHOD, ERR-ANALYS, MONITOR3261601100025
and COMMENT added in BIB-section.- 3261601100026
ENDBIB 24 0 3261601100027
COMMON 5 3 3261601100028
ANG ERR-1 ERR-2 ERR-3 DATA-ERR 3261601100029
ADEG PER-CENT PER-CENT PER-CENT PER-CENT 3261601100030
120. 3. 2. 3. 2. 3261601100031
ENDCOMMON 3 0 3261601100032
DATA 3 21 3261601100033
E DATA ERR-S 3261601100034
MEV MB/SR/MEV PER-CENT 3261601100035
1.85 210.3 4.0000 3261601100036
2.25 63.3000 3.8000 3261601100037
2.65 32.4000 4.4000 3261601100038
3.05 21.9000 5.1000 3261601100039
3.45 17.3000 5.8000 3261601100040
3.85 12.2000 3.0000 3261601100041
4.25 9.4000 3.3000 3261601100042
4.65 6.0000 4.3000 3261601100043
5.05 4.1000 4.9000 3261601100044
5.45 5.8000 4.3000 3261601100045
5.85 3.1000 6.4000 3261601100046
6.25 0.9000 10.6000 3261601100047
6.65 1.2000 5.9000 3261601100048
7.05 1.0000 4.8000 3261601100049
7.45 2.5000 7.7000 3261601100050
7.85 0.5000 14.1000 3261601100051
8.25 0.1000 100.0 3261601100052
8.65 0.7000 15.0000 3261601100053
9.05 6.3000 4.9000 3261601100054
9.45 40.4000 1.9000 3261601100055
9.85 2.7000 7.5000 3261601100056
ENDDATA 23 0 3261601100057
ENDSUBENT 56 0 3261601199999
SUBENT 32616012 20220826 32083261601200001
BIB 7 20 3261601200002
REACTION 1(92-U-238(N,EL)92-U-238,EXL,DA) 3261601200003
2(92-U-238(N,EL)92-U-238,EXL,DA) 3261601200004
CRITIQUE 1Comment by S.Simakov: possible inclusion of inelastic 3261601200005
scattering below Ex ~> 0.74 MeV. 3261601200006
2Comment by S.Simakov: possible inclusion of inelastic 3261601200007
scattering below Ex ~> 0.23 MeV. 3261601200008
REL-REF (C,,S.Simakov+,S,INDC(NDS)-0857,91,2022) 3261601200009
METHOD 1(TOF) An abnormal fast neutron time-of-flight spectro- 3261601200010
meter. 3261601200011
2(TOF) Measurement with a normal TOF spectrometer. 3261601200012
MONITOR 1(6-C-12(N,EL)6-C-12,,DA) 3261601200013
2(1-H-1(N,EL)1-H-1,,DA) Polyethylene is used as the 3261601200014
reference sample. 3261601200015
STATUS (TABLE) Table 3 of J,CNP,14,147,1992 3261601200016
HISTORY (19940615A) HW.- New subent added.- 3261601200017
(19970424A) HW.- Outgoing particle sequence corrected 3261601200018
under MONITOR (2).- 3261601200019
(20220826A) VT. REACTION1,2:SF5->EXL, CRITIQUE, REL-REF3261601200020
added. MONITOR2: SF3:N->EL and 3261601200021
REFERENCE: J,CNP,14,147,1992 deleted 3261601200022
ENDBIB 20 0 3261601200023
NOCOMMON 0 0 3261601200024
DATA 3 3 3261601200025
ANG DATA 1DATA 2 3261601200026
ADEG MB/SR MB/SR 3261601200027
45. 209.6 204.8 3261601200028
90. 29.8 29.4 3261601200029
120. 19.5 20.4 3261601200030
ENDDATA 5 0 3261601200031
ENDSUBENT 30 0 3261601299999
ENDENTRY 12 0 3261699999999