ENTRY 22231 20200808 229022231 0 1 SUBENT 22231001 20200808 229022231 1 1 BIB 15 228 22231 1 2 TITLE Reaction cross sections on carbon for neutron energies22231 1 3 from 11.5 to 19 MeV 22231 1 4 AUTHOR (B.Antolkovic,G.Dietze,H.Klein) 22231 1 5 REFERENCE (J,NSE,107,1,1991) Subents 002-008 data 22231 1 6 (J,RPD,44,31,1992) Subents 009- data 22231 1 7 Secondary alpha particle spectra and partial kerma 22231 1 8 factors of the reaction n + 12C -> n + 3 alpha 22231 1 9 carbon deduced from microscopic cross sections at 22231 1 10 incident neutron energies below 75 MeV . 22231 1 11 INSTITUTE (2GERPTB) G.Dietze, H.Klein and experimental site 22231 1 12 (3CRORBZ) B.Antolkovic 22231 1 13 REL-REF (M,,B.Antolkovic+,J,NP/A,524,285,1991) 22231 1 14 Processing and analysis of data 22231 1 15 FACILITY (VDG,2GERPTB) The PTB Van De Graaff generator was used 22231 1 16 for 13 to 19 MeV neutron energies. 22231 1 17 (ISOCY,2GERPTB) The PTB isochronous cyclotron was used 22231 1 18 for 11.5 to 13.5 MeV neutron energies. 22231 1 19 MONITOR (1-H-1(N,EL)1-H-1,,SIG) Recoil proton measurement 22231 1 20 INC-SOURCE (D-T) Monoenergetic neutrons of energy between 22231 1 21 13 and 19 MeV were produced by bombarding a titanium- 22231 1 22 tritium target with deuterons. Neutrons of 14.8, 17 22231 1 23 and 19 MeV were produced at zero degree with respect 22231 1 24 to the incident beam direction. And neutron with other22231 1 25 energies were produced making use of the energy 22231 1 26 distribution of the reaction. 22231 1 27 . Targets of different thicknesses were used to obtain 22231 1 28 optimum neutron yields. 22231 1 29 . The incident deuteron energy could be specified 22231 1 30 within +/- 2 keV. Using TOF techniques and Monte Carlo22231 1 31 calculations it was deduced that a negligible amount 22231 1 32 of neutrons were produced between 9.5 and 1 MeV below 22231 1 33 the nominal energy. 22231 1 34 . The neutron energy width was determined from the 22231 1 35 energy loss of the deuterons within the gas and the 22231 1 36 neutron energy distribution was assumed to be 22231 1 37 rectangular. 22231 1 38 . Ti-T target,2.40 mg/cm2 Ti on 1-mm-thick Ag, mean 22231 1 39 deuteron energy 2.55 MeV 22231 1 40 Emission angle Mean neutron energy Energy distr.width 22231 1 41 deg MeV MeV 22231 1 42 0.0 19.00 +- 0.030 0.380 22231 1 43 27.65 18.50 +- 0.027 0.350 22231 1 44 39.78 18.00 +- 0.024 0.310 22231 1 45 49.61 17.50 +- 0.022 0.275 22231 1 46 . Ti-T target, 2.29 mg/cm2 Ti on 1-mm-thick Ag, mean 22231 1 47 deuteron energy 1.15 MeV 22231 1 48 Emission angle Mean neutron energy Energy distr.width 22231 1 49 deg MeV MeV 22231 1 50 0.0 17.00 +- 0.050 0.700 22231 1 51 35.55 16.50 +- 0.042 0.600 22231 1 52 51.60 16.00 +- 0.034 0.500 22231 1 53 65.00 15.50 +- 0.027 0.400 22231 1 54 77.40 15.00 +- 0.023 0.300 22231 1 55 82.24 14.80 +- 0.016 0.240 22231 1 56 87.14 14.60 +- 0.014 0.200 22231 1 57 92.07 14.40 +- 0.011 0.160 22231 1 58 97.08 14.20 +- 0.009 0.120 22231 1 59 102.25 14.00 +- 0.006 0.100 22231 1 60 116.03 13.50 +- 0.006 0.050 22231 1 61 132.44 13.00 +- 0.007 0.100 22231 1 62 . Ti-T target, 2.29 mg/cm2 Ti on 1-mm-thick Ag,deuteron22231 1 63 energy 0.2 MeV, neutron emission angle 0.0 deg, 22231 1 64 mean neutron energy 14.80+-0.030 MeV, neutron energy 22231 1 65 distribution width 0.460 MeV. 22231 1 66 (D-D) Monoenergetic neutrons of energy between 22231 1 67 11.5 and 13.5 MeV were produced with the D-D reaction,22231 1 68 using a deuterium gas target and the pulsed deuteron 22231 1 69 beam of the energy variable cyclotron. The mean 22231 1 70 deuteron energy within the gas was implicitly deter- 22231 1 71 mined by neutron time of flight measurements using an 22231 1 72 NE213 detector. An uncertainty of 30 keV was achieved.22231 1 73 The neutron energy width was determined from the 22231 1 74 energy loss of the deuterons within the gas and the 22231 1 75 neutron energy distribution was again assumed to be 22231 1 76 rectangular. 22231 1 77 The D-N and the deuteron breakup reactions on 22231 1 78 molybdenum entrance foil and the gold beam stop 22231 1 79 yielded (15%) neutrons with energies distributed 22231 1 80 equally over a 6 MeV region below the nominal energy. 22231 1 81 . D2 gas target, 3 cm long, 10 kPa D2, mean deuteron 22231 1 82 energy form 8.4 MeV to 10.53 MeV , emission angle 0.deg22231 1 83 Mean neutron energy,MeV Energy distribution width,MeV 22231 1 84 13.535 +- 0.030 0.080 22231 1 85 12.895 +- 0.030 0.085 22231 1 86 12.555 +- 0.030 0.090 22231 1 87 11.915 +- 0.030 0.095 22231 1 88 11.505 +- 0.030 0.100 22231 1 89 INC-SPECT .The neutron fluence applied in the irradiation of the 22231 1 90 emulsions was determined using a proton recoil 22231 1 91 telescope in a geometry similar to that used during 22231 1 92 exposure of the emulsions. The signals from 2 prop. 22231 1 93 counters and a surface barrier detector were analyzed 22231 1 94 in coincidence to distinguish the recoil proton events22231 1 95 from the neutron interaction in a 10.085mg/cm2 thick 22231 1 96 tristearine radiator. 22231 1 97 The detection efficiency was calculated taking into 22231 1 98 account the actual irradiation geometry and the 22231 1 99 evaluated N-P scattering cross section. Two moderating22231 1 100 neutron detectors were used to monitor the fluence 22231 1 101 during irradiation of the emulsions. 22231 1 102 For the cyclotron measurements, the fluence was 22231 1 103 determined using the NE213 liquid scintillator. 22231 1 104 The well known hydrogen content of the scintillator 22231 1 105 was used to normalize to the N-P scattering cross 22231 1 106 section. The total uncertainty was about 3 %, was 22231 1 107 estimated from the fitting procedure, the basic cross 22231 1 108 sections and the hydrogen content. 22231 1 109 SAMPLE .ILFORD C2 nuclear emulsions were used as samples and 22231 1 110 detectors to study the C-12(N,N+3ALPHA).The emulsions 22231 1 111 with a carbon content of 0.277g/cm3 and a thickness 22231 1 112 of 200 micro-meter were exposed at an angle of 13.8 22231 1 113 adeg to monoenergetic neutrons of energies 11.9, 12.9,22231 1 114 14.0, 17.0 and 19.0 MeV. 22231 1 115 .The scintillator which has a well known carbon content22231 1 116 is used as a carbon target as well as an alpha 22231 1 117 detector. 22231 1 118 METHOD (ASSOP) The nuclear emulsion technique was used to 22231 1 119 investigate C-12(N,N+3ALPHA) reaction for neutron 22231 1 120 energies of 11.9 to 19.0 MeV. The total and various 22231 1 121 partial cross sections from the N-3ALPHA breakup 22231 1 122 were determined. 22231 1 123 (TOF) The total cross sections of all reactions with 22231 1 124 charged particles (except carbon recoil protons) in 22231 1 125 the exit channel were determined W.R.T the N-P 22231 1 126 scattering cross section using an NE213 scintillator 22231 1 127 with TOF technique. 22231 1 128 (PHD) The pulse shape discrimination technique was 22231 1 129 used with the NE213 detector. 22231 1 130 DETECTOR (PLATE) The nuclear emulsions which contain carbon 22231 1 131 as a main constituent are used both as a carbon target22231 1 132 and as a alpha-particle detector. The simultaneous 22231 1 133 detection of all charged particles of such an event 22231 1 134 yields a kinematically complete measurement. The 22231 1 135 emulsions were developed by a 2-temperature technique22231 1 136 after which they were scanned for 3-pronged events 22231 1 137 using a Leitz Ortholux binocular microscope.The 22231 1 138 reaction kinematics was determined by measuring the 22231 1 139 spatial orientations and ranges of each of the 3 22231 1 140 prongs of a star . 22231 1 141 (SCIN) The NE213 scintillation detector also served 22231 1 142 both as the carbon target and the alpha particle 22231 1 143 detector. It was used in assessing reactions with 22231 1 144 very low statistical uncertainties. The response 22231 1 145 of this detector, 2.54 cm in height by 10.16 cm in 22231 1 146 diameter, was measured for monoenergetic neutrons 22231 1 147 applying 'TOF' techniques and compared with Monte- 22231 1 148 Carlo simulations. Elastic and inelastic cross 22231 1 149 sections were taken from ENDF/B-V. 22231 1 150 COMMENT Of compiler M.M. Alpha energy diff. CS presented on 22231 1 151 Fig. 1 of J.Radiation Protection Dosimetry,44,31,1992 22231 1 152 have insufficient quality for digitization - 22231 1 153 overlapping, triangles and full points could not be 22231 1 154 separated. 22231 1 155 ADD-RES Distribution of alpha particle spectrum, normalized 22231 1 156 to 1. ( Fig.2 left, right) 22231 1 157 En=17.0 MeV 22231 1 158 Eaplha, MeV Value, no-dim. 22231 1 159 0.079 0.0028 22231 1 160 0.369 0.0325 22231 1 161 0.607 0.0684 22231 1 162 0.862 0.1086 22231 1 163 1.134 0.1467 22231 1 164 1.390 0.1785 22231 1 165 1.629 0.1955 22231 1 166 1.868 0.2104 22231 1 167 2.124 0.2316 22231 1 168 2.414 0.2423 22231 1 169 2.637 0.2467 22231 1 170 2.860 0.2216 22231 1 171 3.135 0.2112 22231 1 172 3.374 0.2282 22231 1 173 3.633 0.1779 22231 1 174 3.890 0.1760 22231 1 175 4.129 0.1803 22231 1 176 4.369 0.1700 22231 1 177 4.626 0.1638 22231 1 178 4.884 0.1430 22231 1 179 5.108 0.1221 22231 1 180 5.348 0.1096 22231 1 181 5.604 0.1182 22231 1 182 5.863 0.0805 22231 1 183 6.103 0.0680 22231 1 184 6.360 0.0577 22231 1 185 6.600 0.0684 22231 1 186 6.858 0.0349 22231 1 187 7.115 0.0308 22231 1 188 7.355 0.0184 22231 1 189 7.612 0.0270 22231 1 190 7.886 0.0250 22231 1 191 8.075 0.0104 22231 1 192 8.366 0.0085 22231 1 193 8.606 0.0066 22231 1 194 8.845 0.0047 22231 1 195 En=12.9 MeV 22231 1 196 Eaplha, MeV Value, no-dim. 22231 1 197 0.086 0.0343 22231 1 198 0.378 0.1291 22231 1 199 0.635 0.2095 22231 1 200 0.893 0.3600 22231 1 201 1.133 0.3930 +- 0.0206 22231 1 202 1.390 0.4527 +- 0.0226 22231 1 203 1.630 0.3743 +- 0.0288 22231 1 204 1.869 0.3022 +- 0.0288 22231 1 205 2.108 0.2774 +- 0.0288 22231 1 206 2.382 0.2526 +- 0.0288 22231 1 207 2.604 0.2217 +- 0.0288 22231 1 208 2.861 0.1515 +- 0.0391 22231 1 209 3.101 0.1866 +- 0.0432 22231 1 210 3.340 0.1412 +- 0.0556 22231 1 211 3.614 0.2009 +- 0.0762 22231 1 212 3.854 0.1226 +- 0.0680 22231 1 213 4.128 0.1267 +- 0.1010 22231 1 214 4.367 0.0730 +- 0.0701 22231 1 215 4.589 0.0524 +- 0.0494 22231 1 216 4.863 0.0256 +- 0.0268 22231 1 217 HISTORY (19930707C) N.O. 22231 1 218 (19961225A) * * Corrected by S. Maev 22231 1 219 MONITOR added; FACILITY, DETECTOR, SAMPLE, ERR-ANALYS 22231 1 220 corrected. DATA-ERR -> ERR-T. Subents 002 and 003; 22231 1 221 006 and 007 were merged. 22231 1 222 (20181111A) M.M. Upper -> lower case correction. 22231 1 223 Dates were corrected for 4-digits year. 22231 1 224 ERR-ANALYS was corrected according to now-days rules. 22231 1 225 Code SPSDD was added in Subent 006 . 22231 1 226 INC-SOURCE, ANALYSIS information was added 22231 1 227 Second ref. was added . Subents 009-011 were added. 22231 1 228 EN-ERR and EN-RSL were added in data Subents. 22231 1 229 (20200808A) SD: Corrections in Subents 006,009,010. 22231 1 230 ENDBIB 228 0 22231 1 231 NOCOMMON 0 0 22231 1 232 ENDSUBENT 231 0 22231 199999 SUBENT 22231002 20181111 227222231 2 1 BIB 8 48 22231 2 2 REACTION (6-C-12(N,N+2A)2-HE-4,ISP,SIG) 22231 2 3 C12(n,n')C12*(3alpha) 22231 2 4 ANALYSIS Data for explosure of emulsions and data analysis: 22231 2 5 En,MeV F,1/cm2 N L,cm Nb/N,% C1*C2 C3 22231 2 6 11.9 1.44E+8 1400 45.0 8.1 1.21 1.88 22231 2 7 12.9 1.48E+8 859 45.0 9.1 1.19 1.58 22231 2 8 14.0 1.36E+8 1516 35.0 8.5 1.18 1.47 22231 2 9 14.8 1.51E+8 982 35.0 8.4 1.18 1.31 22231 2 10 17.0 2.00E+8 925 35.0 6.9 1.17 1.25 22231 2 11 19.0 2.95E+8 913 30.0 7.9 1.17 1.21 22231 2 12 F - neutron fluence, 22231 2 13 N - number of vents, 22231 2 14 L - distance between neutron source and sample, 22231 2 15 Nb - background events, 22231 2 16 C1,C2,C3 - correction factors for loss of events 22231 2 17 - alpha particles leaving emulsion before stopping, 22231 2 18 - alpha track perpendicular to emulsion surface, 22231 2 19 - low-energy alpha particle ( cutoff ~ 0.45 MeV) 22231 2 20 CORRECTION .In the emulsion measurements, corrections were made 22231 2 21 for dead time losses,flux attenuation in air, 22231 2 22 construction materials and radiator backing and for 22231 2 23 a small background peak under the proton recoil peak. 22231 2 24 COMMENT . The data is the partial C-12(N,N3A) 22231 2 25 reaction cross section deduced by subtracting 22231 2 26 C-12(N,A)BE-9(N2A) reaction via the 2.4 MeV 22231 2 27 level of Be-9 from the total C-12(N,N3A) cross 22231 2 28 section. 22231 2 29 EN-SEC (E-EXC,6-C-12) Min/max excitation energy of C-12 22231 2 30 are given in DATA block 22231 2 31 ERR-ANALYS (ERR-T) Total error in the nuclear emulsion 22231 2 32 measurements. Its constituents given below 22231 2 33 (ERR-S,,3.) Max statistical error (3%) 22231 2 34 (ERR-1) Background subtraction error (3 %) 22231 2 35 (ERR-2) Neutron fluence determination error (3 %) 22231 2 36 (ERR-3) Carbon content determination error (2 %) 22231 2 37 (ERR-4,3.,9.6) Corrections error 22231 2 38 Sum of other correction uncertainties 22231 2 39 at 12 MeV neutron energy (9.6 %) 22231 2 40 Sum of correction factor uncertainties 22231 2 41 at 19. MeV neutron energy (3 % ) 22231 2 42 STATUS (TABLE) From Table III of J.Nucl.Sci.Eng.,107,1,1991 22231 2 43 HISTORY (19930701C) N.O. 22231 2 44 (19931129E) 22231 2 45 (19961225A) Data section rearranged and similar data 22231 2 46 from other Subentries moved in this one 22231 2 47 (20181111A) E-EXC-MIN=8MeV added at first point 22231 2 48 instead of blank according to a comment of N.Otsuka 22231 2 49 (NDS,IAEA) 22231 2 50 ENDBIB 48 0 22231 2 51 COMMON 3 3 22231 2 52 ERR-1 ERR-2 ERR-3 22231 2 53 PER-CENT PER-CENT PER-CENT 22231 2 54 3.0 3.0 2.0 22231 2 55 ENDCOMMON 3 0 22231 2 56 DATA 8 32 22231 2 57 EN EN-ERR EN-RSL E-EXC-MIN E-EXC-MAX E-EXC-MEAN 22231 2 58 DATA ERR-T 22231 2 59 MEV MEV MEV MEV MEV MEV 22231 2 60 MB MB 22231 2 61 11.9 0.030 0.095 8. 10.25 9.6 22231 2 62 110.8 17.0 22231 2 63 11.9 0.030 0.095 10.25 11.25 10.8 22231 2 64 16.4 8.6 22231 2 65 11.9 0.030 0.095 11.25 12.25 11.8 22231 2 66 1.6 0.5 22231 2 67 12.9 0.030 0.085 8. 10.25 9.6 22231 2 68 71.7 8.5 22231 2 69 12.9 0.030 0.085 10.25 11.25 10.8 22231 2 70 49.8 12.4 22231 2 71 12.9 0.030 0.085 11.25 12.25 11.8 22231 2 72 7.4 7.0 22231 2 73 12.9 0.030 0.085 12.25 13.50 12.8 22231 2 74 1.2 1.0 22231 2 75 14.0 0.006 0.100 8. 10.25 9.6 22231 2 76 76.5 8.0 22231 2 77 14.0 0.006 0.100 10.25 11.25 10.8 22231 2 78 47.0 3.6 22231 2 79 14.0 0.006 0.100 11.25 12.25 11.8 22231 2 80 37.6 12.2 22231 2 81 14.0 0.006 0.100 12.25 13.50 12.8 22231 2 82 8.4 5.9 22231 2 83 14.8 0.030 0.460 8. 10.25 9.6 22231 2 84 69.0 8.4 22231 2 85 14.8 0.030 0.460 10.25 11.25 10.8 22231 2 86 36.1 4.0 22231 2 87 14.8 0.030 0.460 11.25 12.25 11.8 22231 2 88 50.2 4.9 22231 2 89 14.8 0.030 0.460 12.25 13.50 12.8 22231 2 90 48.7 12.1 22231 2 91 14.8 0.030 0.460 13.50 14.50 14.0 22231 2 92 5.6 0.7 22231 2 93 17.0 0.050 0.700 8. 10.25 9.6 22231 2 94 44.5 4.9 22231 2 95 17.0 0.050 0.700 10.25 11.25 10.8 22231 2 96 25.0 2.5 22231 2 97 17.0 0.050 0.700 11.25 12.25 11.8 22231 2 98 35.7 2.8 22231 2 99 17.0 0.050 0.700 12.25 13.50 12.8 22231 2 100 71.1 4.1 22231 2 101 17.0 0.050 0.700 13.50 14.50 14.0 22231 2 102 42.9 5.9 22231 2 103 17.0 0.050 0.700 14.50 15.50 15.0 22231 2 104 29.4 5.4 22231 2 105 17.0 0.050 0.700 15.50 16.50 16.0 22231 2 106 9.4 2.8 22231 2 107 19.0 0.030 0.380 8. 10.25 9.6 22231 2 108 45.9 5.3 22231 2 109 19.0 0.030 0.380 10.25 11.25 10.8 22231 2 110 21.3 2.8 22231 2 111 19.0 0.030 0.380 11.25 12.25 11.8 22231 2 112 33.3 3.2 22231 2 113 19.0 0.030 0.380 12.25 13.50 12.8 22231 2 114 39.4 3.4 22231 2 115 19.0 0.030 0.380 13.50 14.50 14.0 22231 2 116 39.9 3.5 22231 2 117 19.0 0.030 0.380 14.50 15.50 15.0 22231 2 118 44.1 3.4 22231 2 119 19.0 0.030 0.380 15.50 16.50 16.0 22231 2 120 41.3 6.1 22231 2 121 19.0 0.030 0.380 16.50 17.50 17.0 22231 2 122 18.4 4.8 22231 2 123 19.0 0.030 0.380 17.50 18.50 18.0 22231 2 124 7.4 2.6 22231 2 125 ENDDATA 68 0 22231 2 126 ENDSUBENT 125 0 22231 299999 NOSUBENT 22231003 20181111 227222231 3 1 SUBENT 22231004 20181111 227222231 4 1 BIB 7 43 22231 4 2 REACTION (6-C-12(N,A)4-BE-9,PAR,SIG) 22231 4 3 ANALYSIS Data for explosure of emulsions and data analysis: 22231 4 4 En,MeV F,1/cm2 N L,cm Nb/N,% C1*C2 C3 22231 4 5 11.9 1.44E+8 1400 45.0 8.1 1.21 1.88 22231 4 6 12.9 1.48E+8 859 45.0 9.1 1.19 1.58 22231 4 7 14.0 1.36E+8 1516 35.0 8.5 1.18 1.47 22231 4 8 14.8 1.51E+8 982 35.0 8.4 1.18 1.31 22231 4 9 17.0 2.00E+8 925 35.0 6.9 1.17 1.25 22231 4 10 19.0 2.95E+8 913 30.0 7.9 1.17 1.21 22231 4 11 F - neutron fluence, 22231 4 12 N - number of vents, 22231 4 13 L - distance between neutron source and sample, 22231 4 14 Nb - background events, 22231 4 15 C1,C2,C3 - correction factors for loss of events 22231 4 16 - alpha particles leaving emulsion before stopping, 22231 4 17 - alpha track perpendicular to emulsion surface, 22231 4 18 - low-energy alpha particle ( cutoff ~ 0.45 MeV) 22231 4 19 CORRECTION .In the emulsion measurements, corrections were made 22231 4 20 for dead time losses,flux attenuation in air, 22231 4 21 construction materials and radiator backing and for 22231 4 22 a small background peak under the proton recoil peak. 22231 4 23 COMMENT .The data is the contribution of the partial 22231 4 24 C-12(N,A)BE-9(N+2A) reaction via the 2.4 MeV level of 22231 4 25 Be-9 to the total C-12(N,N+3A) cross section. It has 22231 4 26 been extracted considering kinematical conditions. 22231 4 27 ERR-ANALYS (ERR-T) Total error in the nuclear emulsion 22231 4 28 measurements. Its constituents given below 22231 4 29 (ERR-S,,3.) Max statistical error (3%) 22231 4 30 (ERR-1) Background subtraction error (3 %) 22231 4 31 (ERR-2) Neutron fluence determination error (3 %) 22231 4 32 (ERR-3) Carbon content determination error (2 %) 22231 4 33 (ERR-4,3.,9.6) Corrections error 22231 4 34 Sum of other correction uncertainties 22231 4 35 at 12 MeV neutron energy (9.6 %) 22231 4 36 Sum of correction factor uncertainties 22231 4 37 at 19. MeV neutron energy (3 % ) 22231 4 38 STATUS (TABLE) From Table III of J.Nucl.Sci.Eng.,107,1,1991 22231 4 39 HISTORY (19930707C) N.O. 22231 4 40 (19931129E) 22231 4 41 (19961225U) Excitation energy is introduced 22231 4 42 (20181111A) Reaction was corrected : 22231 4 43 6-C-12(N,N+2A)2-HE-4,PAR,SIG -> 22231 4 44 6-C-12(N,A)4-BE-9,PAR,SIG ; E-EXC -> E-LVL 22231 4 45 ENDBIB 43 0 22231 4 46 COMMON 4 3 22231 4 47 E-LVL ERR-1 ERR-2 ERR-3 22231 4 48 MEV PER-CENT PER-CENT PER-CENT 22231 4 49 2.43 3.0 3.0 2.0 22231 4 50 ENDCOMMON 3 0 22231 4 51 DATA 5 6 22231 4 52 EN EN-ERR EN-RSL DATA ERR-T 22231 4 53 MEV MEV MEV MB MB 22231 4 54 11.9 0.030 0.095 48.0 12.0 22231 4 55 12.9 0.030 0.085 37.0 17.0 22231 4 56 14.0 0.006 0.100 32.0 20.0 22231 4 57 14.8 0.016 0.240 18.0 14.0 22231 4 58 17.0 0.050 0.700 14.0 8.0 22231 4 59 19.0 0.030 0.380 9.0 9.0 22231 4 60 ENDDATA 8 0 22231 4 61 ENDSUBENT 60 0 22231 499999 SUBENT 22231005 20181111 227222231 5 1 BIB 7 46 22231 5 2 REACTION (6-C-12(N,N+2A)2-HE-4,,SIG,,MSC) 22231 5 3 12C(n,n+3a) cross section excluding 12C(n,n2)12C 22231 5 4 contribution 22231 5 5 ANALYSIS Data for explosure of emulsions and data analysis: 22231 5 6 En,MeV F,1/cm2 N L,cm Nb/N,% C1*C2 C3 22231 5 7 11.9 1.44E+8 1400 45.0 8.1 1.21 1.88 22231 5 8 12.9 1.48E+8 859 45.0 9.1 1.19 1.58 22231 5 9 14.0 1.36E+8 1516 35.0 8.5 1.18 1.47 22231 5 10 14.8 1.51E+8 982 35.0 8.4 1.18 1.31 22231 5 11 17.0 2.00E+8 925 35.0 6.9 1.17 1.25 22231 5 12 19.0 2.95E+8 913 30.0 7.9 1.17 1.21 22231 5 13 F - neutron fluence, 22231 5 14 N - number of vents, 22231 5 15 L - distance between neutron source and sample, 22231 5 16 Nb - background events, 22231 5 17 C1,C2,C3 - correction factors for loss of events 22231 5 18 - alpha particles leaving emulsion before stopping, 22231 5 19 - alpha track perpendicular to emulsion surface, 22231 5 20 - low-energy alpha particle ( cutoff ~ 0.45 MeV) 22231 5 21 CORRECTION .In the emulsion measurements, corrections were made 22231 5 22 for dead time losses,flux attenuation in air, 22231 5 23 construction materials and radiator backing and for 22231 5 24 a small background peak under the proton recoil peak. 22231 5 25 COMMENT .Data is the total C-12(N,N3A) reaction cross sections 22231 5 26 including C-12(N,A)BE-9(N+2A) reaction via the 2.4 MeV22231 5 27 level of Be-9 and all inelastic channels except the 22231 5 28 inel. scat. via the 7.6 MeV level of carbon. 22231 5 29 ERR-ANALYS (ERR-T) Total error in the nuclear emulsion 22231 5 30 measurements. Its constituents given below 22231 5 31 (ERR-S,,3.) Max statistical error (3%) 22231 5 32 (ERR-1) Background subtraction error (3 %) 22231 5 33 (ERR-2) Neutron fluence determination error (3 %) 22231 5 34 (ERR-3) Carbon content determination error (2 %) 22231 5 35 (ERR-4,3.,9.6) Corrections error 22231 5 36 Sum of other correction uncertainties 22231 5 37 at 12 MeV neutron energy (9.6 %) 22231 5 38 Sum of correction factor uncertainties 22231 5 39 at 19. MeV neutron energy (3 % ) 22231 5 40 STATUS (TABLE) From Table III of J.Nucl.Sci.Eng.,107,1,1991 22231 5 41 (DEP,22231002) 22231 5 42 (DEP,22231004) 22231 5 43 HISTORY (19930707C) N.O. 22231 5 44 (19931129E) 22231 5 45 (19961225U) Cross-reference is given 22231 5 46 (20181111A) MSC code was added according to a comment 22231 5 47 of N.Otsuka (NDS,IAEA) 22231 5 48 ENDBIB 46 0 22231 5 49 COMMON 3 3 22231 5 50 ERR-1 ERR-2 ERR-3 22231 5 51 PER-CENT PER-CENT PER-CENT 22231 5 52 3.0 3.0 2.0 22231 5 53 ENDCOMMON 3 0 22231 5 54 DATA 5 6 22231 5 55 EN EN-ERR EN-RSL DATA ERR-T 22231 5 56 MEV MEV MEV MB MB 22231 5 57 11.9 0.030 0.095 176.8 18.2 22231 5 58 12.9 0.030 0.085 167.1 14.0 22231 5 59 14.0 0.006 0.100 210.5 14.6 22231 5 60 14.8 0.016 0.240 227.6 14.8 22231 5 61 17.0 0.050 0.700 272.0 16.9 22231 5 62 19.0 0.030 0.380 300.0 17.9 22231 5 63 ENDDATA 8 0 22231 5 64 ENDSUBENT 63 0 22231 599999 SUBENT 22231006 20200808 229022231 6 1 BIB 8 58 22231 6 2 REACTION (6-C-12(N,N+A)4-BE-8,ISP/PAR,SIG,,MSC) 22231 6 3 cross section for all (n,n3a) reactions via 8Be(g.s.) 22231 6 4 and characterized by the three-alpha energy 22231 6 5 ANALYSIS Data for exposure of emulsions and data analysis: 22231 6 6 En,MeV F,1/cm2 N L,cm Nb/N,% C1*C2 C3 22231 6 7 11.9 1.44E+8 1400 45.0 8.1 1.21 1.88 22231 6 8 12.9 1.48E+8 859 45.0 9.1 1.19 1.58 22231 6 9 14.0 1.36E+8 1516 35.0 8.5 1.18 1.47 22231 6 10 14.8 1.51E+8 982 35.0 8.4 1.18 1.31 22231 6 11 17.0 2.00E+8 925 35.0 6.9 1.17 1.25 22231 6 12 19.0 2.95E+8 913 30.0 7.9 1.17 1.21 22231 6 13 F - neutron fluence, 22231 6 14 N - number of vents, 22231 6 15 L - distance between neutron source and sample, 22231 6 16 Nb - background events, 22231 6 17 C1,C2,C3 - correction factors for loss of events 22231 6 18 - alpha particles leaving emulsion before stopping, 22231 6 19 - alpha track perpendicular to emulsion surface, 22231 6 20 - low-energy alpha particle ( cutoff ~ 0.45 MeV) 22231 6 21 CORRECTION .In the emulsion measurements, corrections were made 22231 6 22 for dead time losses,flux attenuation in air, 22231 6 23 construction materials and radiator backing and for 22231 6 24 a small background peak under the proton recoil peak. 22231 6 25 COMMENT .The partial cross sections for the transition via 22231 6 26 the 8-Be ground state in the C-12(N,N3A) breakup 22231 6 27 reaction was extracted from experimental data and 22231 6 28 given in table IV as below. 12-C(N,A)9-BE contribution22231 6 29 is included 22231 6 30 EN-SEC (E-EXC,6-C-12) (Min., max, mean) excitation energy of 22231 6 31 intermediate nucleus. 12-C excitation energy bins 22231 6 32 overlap with reaction 12-C(N,A)9-BE 22231 6 33 (E-LVL,4-BE-8) 22231 6 34 ERR-ANALYS (ERR-T) Total error in the nuclear emulsion 22231 6 35 measurements. Its constituents given below 22231 6 36 (ERR-S,,3.) Max statistical error (3%) 22231 6 37 (ERR-1) Background subtraction error (3 %) 22231 6 38 (ERR-2) Neutron fluence determination error (3 %) 22231 6 39 (ERR-3) Carbon content determination error (2 %) 22231 6 40 (ERR-4,3.,9.6) Corrections error 22231 6 41 Sum of other correction uncertainties 22231 6 42 at 12 MeV neutron energy (9.6 %) 22231 6 43 Sum of correction factor uncertainties 22231 6 44 at 19. MeV neutron energy (3 % ) 22231 6 45 STATUS (TABLE) From Table IV of J.Nucl.Sci.Eng.,107,1,1991 22231 6 46 (SPSDD,22231009) This Subent is superseded by data of 22231 6 47 newer publication in Subent 22231009 22231 6 48 HISTORY (19930707C) N.O. 22231 6 49 (19931129E) 22231 6 50 (19961225A) .Excitation energy is introduced and 22231 6 51 sigma contributions specified 22231 6 52 .Data moved from SUBENT 007 in this one 22231 6 53 (20181111A) M.M. Code SPSDD was added. 22231 6 54 Reaction was corrected : 22231 6 55 (N,N+2A)2-HE-4,PAR,SIG -> (N,N+A)4-BE-8,ISP/PAR,SIG ; 22231 6 56 E-EXC-MIN=8.MeV was added at first poin instead of 22231 6 57 blank. 22231 6 58 (20200808A) SD: SF8=MSC added to REACTION code with 22231 6 59 explanation. 22231 6 60 ENDBIB 58 0 22231 6 61 COMMON 4 3 22231 6 62 E-LVL ERR-1 ERR-2 ERR-3 22231 6 63 MEV PER-CENT PER-CENT PER-CENT 22231 6 64 0. 3.0 3.0 2.0 22231 6 65 ENDCOMMON 3 0 22231 6 66 DATA 8 32 22231 6 67 EN EN-ERR EN-RSL E-EXC-MIN E-EXC-MAX E-EXC-MEAN 22231 6 68 DATA ERR-T 22231 6 69 MEV MEV MEV MEV MEV MEV 22231 6 70 MB MB 22231 6 71 11.9 0.030 0.095 8. 10.25 9.6 22231 6 72 113.0 12.8 22231 6 73 11.9 0.030 0.095 10.25 11.25 10.8 22231 6 74 21.0 3.0 22231 6 75 11.9 0.030 0.095 11.25 12.25 11.8 22231 6 76 1.5 0.7 22231 6 77 12.9 0.030 0.085 8. 10.25 9.6 22231 6 78 67.3 8.3 22231 6 79 12.9 0.030 0.085 10.25 11.25 10.8 22231 6 80 51.6 4.7 22231 6 81 12.9 0.030 0.085 11.25 12.25 11.8 22231 6 82 10.3 1.7 22231 6 83 12.9 0.030 0.085 12.25 13.50 12.8 22231 6 84 0.7 0.5 22231 6 85 14.0 0.006 0.100 8. 10.25 9.6 22231 6 86 67.3 7.2 22231 6 87 14.0 0.006 0.100 10.25 11.25 10.8 22231 6 88 30.8 2.6 22231 6 89 14.0 0.006 0.100 11.25 12.25 11.8 22231 6 90 20.6 1.8 22231 6 91 14.0 0.006 0.100 12.25 13.50 12.8 22231 6 92 6.3 0.9 22231 6 93 14.8 0.030 0.460 8. 10.25 9.6 22231 6 94 64.3 8.1 22231 6 95 14.8 0.030 0.460 10.25 11.25 10.8 22231 6 96 22.5 2.9 22231 6 97 14.8 0.030 0.460 11.25 12.25 11.8 22231 6 98 20.6 2.6 22231 6 99 14.8 0.030 0.460 12.25 13.50 12.8 22231 6 100 16.7 2.0 22231 6 101 14.8 0.030 0.460 13.50 14.50 14.0 22231 6 102 1.1 0.3 22231 6 103 17.0 0.050 0.700 8. 10.25 9.6 22231 6 104 36.6 4.2 22231 6 105 17.0 0.050 0.700 10.25 11.25 10.8 22231 6 106 14.7 1.8 22231 6 107 17.0 0.050 0.700 11.25 12.25 11.8 22231 6 108 11.9 1.5 22231 6 109 17.0 0.050 0.700 12.25 13.50 12.8 22231 6 110 17.6 1.9 22231 6 111 17.0 0.050 0.700 13.50 14.50 14.0 22231 6 112 10.7 1.4 22231 6 113 17.0 0.050 0.700 14.50 15.50 15.0 22231 6 114 6.8 1.1 22231 6 115 17.0 0.050 0.700 15.50 16.50 16.0 22231 6 116 1.4 0.8 22231 6 117 19.0 0.030 0.380 8. 10.25 9.6 22231 6 118 42.3 5.0 22231 6 119 19.0 0.030 0.380 10.25 11.25 10.8 22231 6 120 10.7 1.9 22231 6 121 19.0 0.030 0.380 11.25 12.25 11.8 22231 6 122 6.0 1.3 22231 6 123 19.0 0.030 0.380 12.25 13.50 12.8 22231 6 124 6.0 1.1 22231 6 125 19.0 0.030 0.380 13.50 14.50 14.0 22231 6 126 7.3 1.4 22231 6 127 19.0 0.030 0.380 14.50 15.50 15.0 22231 6 128 3.6 0.9 22231 6 129 19.0 0.030 0.380 15.50 16.50 16.0 22231 6 130 5.1 1.1 22231 6 131 19.0 0.030 0.380 16.50 17.50 17.0 22231 6 132 2.5 0.8 22231 6 133 19.0 0.030 0.380 17.50 18.50 18.0 22231 6 134 0.5 0.4 22231 6 135 ENDDATA 68 0 22231 6 136 ENDSUBENT 135 0 22231 699999 NOSUBENT 22231007 20181111 227222231 7 1 SUBENT 22231008 20181111 227222231 8 1 BIB 9 64 22231 8 2 REACTION (6-C-12(N,N+2A)2-HE-4,,SIG,,MSC) 22231 8 3 Three-alpha break up cross section (excluding 22231 8 4 12C(n,n'2)12C(7.65MeV)(3alpha) contribution) plus 22231 8 5 12C(n,alpha0)9Be cross section. 22231 8 6 PART-DET (A) 22231 8 7 ANALYSIS Data for explosure of emulsions and data analysis: 22231 8 8 En,MeV F,1/cm2 N L,cm Nb/N,% C1*C2 C3 22231 8 9 11.9 1.44E+8 1400 45.0 8.1 1.21 1.88 22231 8 10 12.9 1.48E+8 859 45.0 9.1 1.19 1.58 22231 8 11 14.0 1.36E+8 1516 35.0 8.5 1.18 1.47 22231 8 12 14.8 1.51E+8 982 35.0 8.4 1.18 1.31 22231 8 13 17.0 2.00E+8 925 35.0 6.9 1.17 1.25 22231 8 14 19.0 2.95E+8 913 30.0 7.9 1.17 1.21 22231 8 15 F - neutron fluence, 22231 8 16 N - number of vents, 22231 8 17 L - distance between neutron source and sample, 22231 8 18 Nb - background events, 22231 8 19 C1,C2,C3 - correction factors for loss of events 22231 8 20 - alpha particles leaving emulsion before stopping, 22231 8 21 - alpha track perpendicular to emulsion surface, 22231 8 22 - low-energy alpha particle ( cutoff ~ 0.45 MeV) 22231 8 23 CORRECTION .In the emulsion measurements, corrections were made 22231 8 24 for dead time losses,flux attenuation in air, 22231 8 25 construction materials and radiator backing and for 22231 8 26 a small background peak under the proton recoil peak. 22231 8 27 COMMENT .Data is the sum of the neutron cross sections 22231 8 28 C-12(N,N3A) including all channels except that for the22231 8 29 sequential decay via the 7.65 MeV level of carbon for 22231 8 30 which the 3alpha particle events can not be separated 22231 8 31 from the carbon recoils. These n-induced reaction 22231 8 32 cross-sections were deduced from the integral 22231 8 33 of the difference spectra. 22231 8 34 REL-REF (A,22075184,A.Takahashi+,J,NST,25,215,1988) 22231 8 35 Ref. NST,25,215,1988 is REL-REF in 22075 . 22231 8 36 (A,,N.Olsson+,J,PMB,34,909,1989) 22231 8 37 (D,12899003,R.C.Haight+,J,NSE,87,41,1984) 22231 8 38 (A,22077001,M.Baba+,C,88MITO,,209,1988) 22231 8 39 (A,,L.F.Hansen,R,UCRL-95890,1986) Recommended data. 22231 8 40 (A,,R.Boettger+,C,85SANTA,2,1455,1985) 22231 8 41 (A,,W.Tornow,W,TORNOW,1988) 22231 8 42 (D,12890001,D.W.Glasgow+,J,NSE,61,521,1976) 22231 8 43 + priv.com.,1982 22231 8 44 ( no (n,n+3a) data in NSE, probably from private 22231 8 45 communication) 22231 8 46 ERR-ANALYS (ERR-T) Total error in the nuclear emulsion 22231 8 47 measurements. Its constituents given below 22231 8 48 (ERR-S,,3.) Max statistical error (3%) 22231 8 49 (ERR-1) Background subtraction error (3 %) 22231 8 50 (ERR-2) Neutron fluence determination error (3 %) 22231 8 51 (ERR-3) Carbon content determination error (2 %) 22231 8 52 (ERR-4,3.,9.6) Corrections error 22231 8 53 Sum of other correction uncertainties 22231 8 54 at 12 MeV neutron energy (9.6 %) 22231 8 55 Sum of correction factor uncertainties 22231 8 56 at 19. MeV neutron energy (3 % ) 22231 8 57 STATUS (TABLE) From Table V of J.Nucl.Sci.Eng.,107,1,1991 22231 8 58 (DEP,22231005) 22231 8 59 (DEP,22231006) 22231 8 60 HISTORY (19930701C) N.O. 22231 8 61 (19931129E) 22231 8 62 (19961225U) Cross-reference to independent data is 22231 8 63 given 22231 8 64 (20181111A) M.M. REL-REFs were added. 22231 8 65 Reactions was corrected : MSC code was added in SF8 22231 8 66 ENDBIB 64 0 22231 8 67 COMMON 3 3 22231 8 68 ERR-1 ERR-2 ERR-3 22231 8 69 PER-CENT PER-CENT PER-CENT 22231 8 70 3.0 3.0 2.0 22231 8 71 ENDCOMMON 3 0 22231 8 72 DATA 5 21 22231 8 73 EN EN-ERR EN-RSL DATA ERR-T 22231 8 74 MEV MEV MEV MB MB 22231 8 75 11.51 0.030 0.100 223.9 8.5 22231 8 76 11.92 0.030 0.095 283.2 9.1 22231 8 77 12.56 0.030 0.090 238.8 9.8 22231 8 78 12.90 0.030 0.085 289.6 10.4 22231 8 79 13.0 0.007 0.100 287.6 9.5 22231 8 80 13.5 0.006 0.050 283.3 8.4 22231 8 81 13.53 0.030 0.080 281.9 9.3 22231 8 82 14.0 0.006 0.100 272.6 8.9 22231 8 83 14.2 0.009 0.120 272.0 9.3 22231 8 84 14.4 0.011 0.160 303.9 9.9 22231 8 85 14.6 0.014 0.200 320.8 11.3 22231 8 86 14.8 0.016 0.240 311.3 11.1 22231 8 87 15.0 0.023 0.300 311.3 10.1 22231 8 88 15.5 0.027 0.400 327.1 12.1 22231 8 89 16.0 0.034 0.500 355.4 12.9 22231 8 90 16.5 0.042 0.600 405.1 15.7 22231 8 91 17.0 0.050 0.700 392.9 16.7 22231 8 92 17.5 0.022 0.275 435.5 19.8 22231 8 93 18.0 0.024 0.310 394.1 23.0 22231 8 94 18.5 0.027 0.350 411.6 20.2 22231 8 95 19.0 0.030 0.380 379.6 19.9 22231 8 96 ENDDATA 23 0 22231 8 97 ENDSUBENT 96 0 22231 899999 SUBENT 22231009 20200808 229022231 9 1 BIB 7 18 22231 9 2 REACTION (6-C-12(N,N+A)4-BE-8,ISP/PAR,SIG,,MSC) 22231 9 3 cross section for all (n,n3a) reactions via 8Be(g.s.) 22231 9 4 and characterized by the three-alpha energy 22231 9 5 EN-SEC (E-EXC,6-C-12) Min., max. and mean energies in DATA 22231 9 6 block are given. 22231 9 7 (E-LVL,4-BE-8) 22231 9 8 ANALYSIS Data of 22231.006 were re-analyzed 22231 9 9 CORRECTION Low energy cut-off, Tables 1, 2 of J.Radiation 22231 9 10 Protection Dosimetry,44,31,1992 data were used as input22231 9 11 in Monte Carlo calculation by E-cut-off = 0.45 MeV . 22231 9 12 ERR-ANALYS (ERR-T) Total error 22231 9 13 (ERR-1,,10.) Correction uncertainty less 10.% 22231 9 14 STATUS (TABLE) Table 1 of J.Radiation Protection Dosimetry,44,22231 9 15 31,1992 22231 9 16 This Subent supersedes Subent 22231.006 22231 9 17 HISTORY (20181111C) M.M. Subent was added. 22231 9 18 (20200808A) SD: SF8=MSC added to REACTION code with 22231 9 19 explanation. 22231 9 20 ENDBIB 18 0 22231 9 21 COMMON 1 3 22231 9 22 E-LVL 22231 9 23 MEV 22231 9 24 0. 22231 9 25 ENDCOMMON 3 0 22231 9 26 DATA 8 33 22231 9 27 EN EN-ERR EN-RSL E-EXC-MIN E-EXC-MAX E-EXC-MEAN 22231 9 28 DATA ERR-T 22231 9 29 MEV MEV MEV MEV MEV MEV 22231 9 30 MB MB 22231 9 31 11.9 0.030 0.095 8. 10.25 9.6 22231 9 32 134.8 4.6 22231 9 33 11.9 0.030 0.095 10.25 11.25 10.75 22231 9 34 21.0 3.0 22231 9 35 11.9 0.030 0.095 11.25 12.25 11.75 22231 9 36 1.5 0.7 22231 9 37 12.9 0.030 0.085 8. 10.25 9.6 22231 9 38 71.7 8.5 22231 9 39 12.9 0.030 0.085 10.25 11.25 10.75 22231 9 40 51.6 4.7 22231 9 41 12.9 0.030 0.085 11.25 12.25 11.75 22231 9 42 10.3 1.7 22231 9 43 12.9 0.030 0.085 12.25 13.25 12.75 22231 9 44 0.7 0.5 22231 9 45 14.0 0.006 0.100 8. 10.25 9.6 22231 9 46 76.5 8.1 22231 9 47 14.0 0.006 0.100 10.25 11.25 10.75 22231 9 48 30.8 2.6 22231 9 49 14.0 0.006 0.100 11.25 12.25 11.75 22231 9 50 23.1 1.8 22231 9 51 14.0 0.006 0.100 12.25 13.25 12.75 22231 9 52 4.5 0.6 22231 9 53 14.0 0.006 0.100 13.25 14.25 13.75 22231 9 54 0.5 0.2 22231 9 55 14.8 0.016 0.240 8. 10.25 9.6 22231 9 56 69.0 8.4 22231 9 57 14.8 0.016 0.240 10.25 11.25 10.75 22231 9 58 22.5 2.9 22231 9 59 14.8 0.016 0.240 11.25 12.25 11.75 22231 9 60 20.6 2.6 22231 9 61 14.8 0.016 0.240 12.25 13.25 12.75 22231 9 62 15.1 1.9 22231 9 63 14.8 0.016 0.240 13.25 14.25 13.75 22231 9 64 2.7 0.7 22231 9 65 17.0 0.050 0.700 8. 10.25 9.6 22231 9 66 44.5 4.9 22231 9 67 17.0 0.050 0.700 10.25 11.25 10.75 22231 9 68 14.7 1.8 22231 9 69 17.0 0.050 0.700 11.25 12.25 11.75 22231 9 70 11.9 1.5 22231 9 71 17.0 0.050 0.700 12.25 13.25 12.75 22231 9 72 14.6 1.8 22231 9 73 17.0 0.050 0.700 13.25 14.25 13.75 22231 9 74 11.2 1.5 22231 9 75 17.0 0.050 0.700 14.25 15.25 14.75 22231 9 76 8.9 1.4 22231 9 77 17.0 0.050 0.700 15.25 16.25 15.75 22231 9 78 1.9 0.9 22231 9 79 19.0 0.030 0.380 8. 10.25 9.6 22231 9 80 45.9 5.3 22231 9 81 19.0 0.030 0.380 10.25 11.25 10.75 22231 9 82 10.7 1.9 22231 9 83 19.0 0.030 0.380 11.25 12.25 11.75 22231 9 84 6.0 1.3 22231 9 85 19.0 0.030 0.380 12.25 13.25 12.75 22231 9 86 4.7 1.0 22231 9 87 19.0 0.030 0.380 13.25 14.25 13.75 22231 9 88 5.7 1.1 22231 9 89 19.0 0.030 0.380 14.25 15.25 14.75 22231 9 90 5.5 1.1 22231 9 91 19.0 0.030 0.380 15.25 16.25 15.75 22231 9 92 4.7 1.0 22231 9 93 19.0 0.030 0.380 16.25 17.25 16.75 22231 9 94 3.9 1.0 22231 9 95 19.0 0.030 0.380 17.25 18.25 17.75 22231 9 96 0.5 0.4 22231 9 97 ENDDATA 70 0 22231 9 98 ENDSUBENT 97 0 22231 999999 SUBENT 22231010 20200808 229022231 10 1 BIB 7 17 22231 10 2 REACTION (6-C-12(N,N+A)4-BE-8,ISP/PAR,SIG,,MSC) 22231 10 3 cross section for all (n,n3a) reactions via 8Be(g.s.) 22231 10 4 and characterized by the three-alpha energy 22231 10 5 EN-SEC (E-EXC,6-C-12) Min., max. and mean energies in DATA 22231 10 6 block are given. 22231 10 7 (LVL-NUMB,4-BE-8) 22231 10 8 ANALYSIS Data of 22231.006 were re-analyzed 22231 10 9 CORRECTION Low energy cut-off, Tables 1, 2 of J.Radiation 22231 10 10 Protection Dosimetry,44,31,1992 data were used as input22231 10 11 in Monte Carlo calculation by E-cut-off = 0.45 MeV . 22231 10 12 ERR-ANALYS (ERR-T) Total error 22231 10 13 (ERR-1,,10.) Correction uncertainty less 10.% 22231 10 14 STATUS (TABLE) Table 1 of J.Radiation Protection Dosimetry,44,22231 10 15 31,1992 22231 10 16 HISTORY (20181111C) M.M. Subent was added. 22231 10 17 (20200808A) SD: SF8=MSC added to REACTION code with 22231 10 18 explanation. 22231 10 19 ENDBIB 17 0 22231 10 20 COMMON 1 3 22231 10 21 LVL-NUMB 22231 10 22 NO-DIM 22231 10 23 1. 22231 10 24 ENDCOMMON 3 0 22231 10 25 DATA 8 27 22231 10 26 EN EN-ERR EN-RSL E-EXC-MIN E-EXC-MAX E-EXC-MEAN 22231 10 27 DATA ERR-T 22231 10 28 MEV MEV MEV MEV MEV MEV 22231 10 29 MB MB 22231 10 30 11.9 0.030 0.095 10.25 11.25 10.75 22231 10 31 19.3 2.1 22231 10 32 11.9 0.030 0.095 11.25 12.25 11.75 22231 10 33 0.1 0.1 22231 10 34 12.9 0.030 0.085 10.25 11.25 10.75 22231 10 35 23.7 2.4 22231 10 36 12.9 0.030 0.085 11.25 12.25 11.75 22231 10 37 10.6 1.7 22231 10 38 12.9 0.030 0.085 12.25 13.25 12.75 22231 10 39 0.5 0.3 22231 10 40 14.0 0.006 0.100 10.25 11.25 10.75 22231 10 41 16.1 1.8 22231 10 42 14.0 0.006 0.100 11.25 12.25 11.75 22231 10 43 35.2 2.6 22231 10 44 14.0 0.006 0.100 12.25 13.25 12.75 22231 10 45 14.3 1.9 22231 10 46 14.0 0.006 0.100 13.25 14.25 13.75 22231 10 47 0.7 0.3 22231 10 48 14.8 0.016 0.240 10.25 11.25 10.75 22231 10 49 13.6 1.7 22231 10 50 14.8 0.016 0.240 11.25 12.25 11.75 22231 10 51 32.6 2.5 22231 10 52 14.8 0.016 0.240 12.25 13.25 12.75 22231 10 53 41.1 4.0 22231 10 54 14.8 0.016 0.240 13.25 14.25 13.75 22231 10 55 10.1 1.7 22231 10 56 17.0 0.050 0.700 10.25 11.25 10.75 22231 10 57 10.3 1.6 22231 10 58 17.0 0.050 0.700 11.25 12.25 11.75 22231 10 59 23.8 1.8 22231 10 60 17.0 0.050 0.700 12.25 13.25 12.75 22231 10 61 44.2 3.8 22231 10 62 17.0 0.050 0.700 13.25 14.25 13.75 22231 10 63 39.7 3.5 22231 10 64 17.0 0.050 0.700 14.25 15.25 14.75 22231 10 65 31.8 3.3 22231 10 66 17.0 0.050 0.700 15.25 16.25 15.75 22231 10 67 14.2 2.0 22231 10 68 19.0 0.030 0.380 10.25 11.25 10.75 22231 10 69 10.7 1.7 22231 10 70 19.0 0.030 0.380 11.25 12.25 11.75 22231 10 71 27.2 2.4 22231 10 72 19.0 0.030 0.380 12.25 13.25 12.75 22231 10 73 26.1 2.4 22231 10 74 19.0 0.030 0.380 13.25 14.25 13.75 22231 10 75 31.6 2.8 22231 10 76 19.0 0.030 0.380 14.25 15.25 14.75 22231 10 77 39.6 3.6 22231 10 78 19.0 0.030 0.380 15.25 16.25 15.75 22231 10 79 43.4 3.8 22231 10 80 19.0 0.030 0.380 16.25 17.25 16.75 22231 10 81 28.2 2.6 22231 10 82 19.0 0.030 0.380 17.25 18.25 17.75 22231 10 83 10.2 1.9 22231 10 84 ENDDATA 58 0 22231 10 85 ENDSUBENT 84 0 22231 1099999 SUBENT 22231011 20181030 227222231 11 1 BIB 9 24 22231 11 2 REACTION 1(6-C-12(N,N+2A)2-HE-4,,KER,,,DERIV) Kerma factor KF 22231 11 3 n + 12C -> n + 3 alpha break up reaction. 22231 11 4 2(6-C-12(N,N+2A)2-HE-4,,KE) 22231 11 5 MONITOR 1(6-C-12(N,N+2A)2-HE-4,,SIG) 22231 11 6 MONIT-REF 1(22231001,B.Antolkovic+,J,NSE,107,1,1991) 22231 11 7 ANALYSIS 1 Kerma factor KF = Nc*EPSa*SIG, where 22231 11 8 Nc - number of C-12 nuclides per unit mass, 22231 11 9 EPSa - mean energy transferred to the kinetic energy 22231 11 10 of alpha particles, 22231 11 11 SIG - C12(n,n3alpha) reaction cross section. 22231 11 12 CORRECTION Low energy cut-off, Tables 1, 2 of J.Radiation 22231 11 13 Protection Dosimetry,44,31,1992 data were used as input22231 11 14 in Monte Carlo calculation by E-cut-off = 0.45 MeV . 22231 11 15 REL-REF (A,,B.Antolkovic+,J,RR,97,253,1984) 22231 11 16 Mean energy agree, kerma factors higher 22231 11 17 (D,,R.C.Haight+,J,NSE,87,41,1984) 22231 11 18 KF=0.56+-0.08 at 1.55 MeV 22231 11 19 (D,,G.Buehler+,J,RPD,13,13,1985) 22231 11 20 KF = 0.96+-0.18 at 15. MeV, 0.80+-0.18 at 17.MeV 22231 11 21 ERR-ANALYS (ERR-T) Includes statistical and correction errors. 22231 11 22 (ERR-1,10.) Correction uncertainty less 10.% 22231 11 23 STATUS (TABLE) Table 3 of J.Radiation Protection Dosimetry,44,22231 11 24 31,1992 22231 11 25 HISTORY (20181111C) M.M. Subent was added. 22231 11 26 ENDBIB 24 0 22231 11 27 NOCOMMON 0 0 22231 11 28 DATA 6 6 22231 11 29 EN EN-ERR EN-RSL DATA 1ERR-T 1DATA 222231 11 30 MEV MEV MEV FGY*M2 FGY*M2 MEV 22231 11 31 11.9 0.030 0.095 0.49 0.07 1.17 22231 11 32 12.9 0.030 0.085 0.55 0.07 1.37 22231 11 33 14.0 0.006 0.100 0.75 0.07 1.55 22231 11 34 14.8 0.016 0.240 0.95 0.08 1.74 22231 11 35 17.0 0.050 0.700 1.46 0.13 2.24 22231 11 36 19.0 0.030 0.380 1.98 0.16 2.63 22231 11 37 ENDDATA 8 0 22231 11 38 ENDSUBENT 37 0 22231 1199999 ENDENTRY 11 0 2223199999999