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